Text

Proposed Tech Specs Revising Reporting Requirements Per Generic Ltrs 83-43 & 85-19 & Schedular Requirements for Submitting Radial Peaking Factor Limit Rept.Fee Paid
	ML18094A563
Person / Time
Site:	Salem
Issue date:	07/07/1989
From:	; Public Service Enterprise Group
To:	;
Shared Package
ML18094A562	List: ML18094A561; ML18094A563;
References
	GL-83-43, GL-85-19, NUDOCS 8907170055
	Download: ML18094A563 (254)
	v • d • e

NLR-N89050 LCR 84-01 Revision 2

ATTACHMENT 1 PROPOSED CHANGE TO THE TECHNICAL SPECIFICATIONS FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 I. Description of Change This proposed change revises changes previously submitted as License Change Request (LCR} 8.4-01, Revision 1, dated October 6, 1986. LCR 88-07, dated July 15, 1988, extensively revised Chapter 6 of the Technical Specifications. Per our agreement with the Salem NRC Licensing Project Manager (Mr. J. C. Stone),

Chapter 6 pages from LCR 88-07 were used to prepare this LCR.

The changes are as follows:

1. Change definition 1.27 from "REPORTABLE OCCURRENCE" to "REPORTABLE EVENT", referencing 10CFR50.73. Also, editorial corrections are made to definition 1.32, "STAGGERED TEST BASIS".

2. (Unit 2 only). Editorial revision of Specification 4.2.2.2(c) to incorporate the change to the relationship between the limit for fractional thermal power operation and rated thermal power, as approved in Amendment 6 to the SGS Unit 2 Technical Specifications.

Revise Specification 4.2.2.2(e) and B3/4.2.3 to reference 6.9.1.9.

3. Revision of Specifications 3.3.3.8, 3.3.3.9 and 3.11.3 to delete reference to Specification 6.9.1.9.b and to provide editorial corrections.

4. Revision of Section 3.4.8 (Unit 1) and 3.4.9 (Unit 2) to eliminate those reactor coolant system specific activity limit requirements deemed unnecessary by NRC Generic Letter 85-19. The corresponding BASES sections are revised accordingly.

5. Revision of Specifications 3.11.1.2, 3.11.1.3, 3.11.2.2, 3.11.2.3, 3.11.2.4, 3.11.4, 3.12.1, 3/4.12.2 and 3/4.12.3 to delete reference to Licensee Event Reports and/or to provide editorial corrections. Revise 3.11.2.4 to state that Specification 3.0.3 is not applicable .

6. Revision to tables 3.12-2 and 4.12-1 to change the

REF: LCR 84-01, Revision 2 NLR-N89050 STATE OF NEW JERSEY SS.

COUNTY OF SALEM Steven E. Miltenberger, being duly sworn according to law deposes and says:

I am Vice President and Chief Nuclear Officer of Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated JUL 7 1989 , concerning the Salem Generating Station, Unit Nos. 1 and 2, are true to the best of my knowledge, information and belief.

Subscribed and Sworn ~:: me this {~ day of , 1989

'if~yµ,~~

Notary Public of New Jersey v~~=*~*~:::*~\ r~. rt\l~~HAtl HOTAA'i rt;i.E:'.. ;y; :rsw JERSEY My Commission expires on My Commisslo;*1 . . "'fl'i"'~ ~:.~av S, 1193

NLR-N89050 LCR 84-01 Revision 2

reporting levels and lower limits of detection of radioactivity concentrations of tritium and I-131 for the radiological environmental monitoring program. The changes will allow higher activity levels provided that drinking water pathways are not involved. Also, an editorial correction to table 4.12-1 is made to change "Cs-136" to "Cs-134".

7. Change "General Manager - Nuclear Safety Review" to "General Manager - Quality Assurance and Nuclear Safety" throughout Chapter 6.

8. Revise.Section 6.2.2 to delete Specification 6.2.2(c),

delete references to "Health Physics technician" and provide editorial corrections to Unit 1. Revise table 6.2-1 to include the minimum shift staffing requirements for the radiation protection technicians.

9. Revision of Specifications 6.2.3.1, 6.3.1 and 6.4.2 to reflect shift Technical Advisor accountability to the "Senior Nuclear" Shift Supervisor, Radiation Protection/Chemistry Manager qualifications, and organizational responsibility for Fire Brigade training, respectively .

Revise Section 6.4.1 to replace reference to 10 CFR Part 55, Appendix A and supplemental requirements, with a general reference to 10 CFR Part 55.

10. Revision to Specifications 6.5.1.2, 6.5.1.3 and 6.5.1.5 to change the SORC composition and rules concerning alternate members and quorum requirements, respectively.

11. Revise Specification 6.5.1.6 to simplify the SORC responsibilities with respect to internal distribution of reports and performance of reviews and investigations. Revise 6.5.1.6(a) to require SORC review of procedure changes only if a 10CFR50.59 safety evaluation is required. Revise 6.5.1.6(k) and 6.5.1.6(1) to require SORC review of changes to the Emergency Plan or Fire Protection Plan and their implementing procedures only if a 10CFR50.59 safety evaluation is required (or an evaluation under 10CFR50.54(q) for Emergency Plan changes). Revise Specification 6.5.3.2(d) to replace. the reference to safety significant issues with a ~eference to 10CFR50.59.

Provide editorial clarification to Specification

6.5.1.8(a), with regard to SORC recommendations of NLR-N89050 LCR 84-01 Revision 2 approval or disapproval of items to the General Manager - Salem Operations.

12. Revise Section 6.5.2 to reflect the proposed Nuclear Safety department configuration. The Manager - Offsite Safety Review and the Manager - Onsite Safety Review will be replaced by the Manager - Nuclear Safety, who will have management responsibilty for both the Offsite Safety Review (OSR) staff and the Onsite Safety Review Group ( SRG) .

13. Revise Specification 6.5.2.3 to clarify the use of consultants by the Nuclear Safety Department. Provide editorial revisions to Specification 6.5.2.4. Delete the miscellaneous OSR activities at the end of Specification 6.5.2.4.1. Revise 6.5.2.4~2(g) to add the phrase "that could affect nuclear safety."

14. Revision to Specification 6.5.2.4.3(i) and 6.5.2.4.3(j) to specify that either offsite fire protection engineers or independent fire protection consultants will be utilized for the fire protection and loss prevention program implementation audits, with an outside consultant being used at least once per 36 months.

15. Delete Specification 6.5.2.7 and insert new Specification 6.5.2.4.4. This will clarify that the record requirements described therein pertain specifically to the OSR staff. It will also change the allowable time periods for forwarding reports of reviews and audits. *

16. Revise Section 6.5.3 to replace "NSR" with "the OSR staff".

17. Revision of the title of Section 6.9 to delete reference to reportable occurrences. Revision to Section 6.9.1 and 6.9.2 to refer specifically to USNRC Region I.

Revision to Specification 6.9.1.4 to delete requirements for submittal of the initial Annual Report.

18. Addition of Specification 6.9.1.5c to include primary coolant specific activity analyses results among the annual reports.

19. Deletion of Specifications 6.9.1.7, 6.9.1.8 and 6.9.1.9 to reflect reporting requirements of 10CFR50.73, consistent with NRC Generic Letter 83-43. Renumbering of Specifications 6.9.1.10 and 6.9.1.11 and other editorial revisions .

NLR-N89050 LCR 84-01 Revision 2

20. Revision of the requirements of Specification 6.9.1.7 (formerly 6.9.1.10) regarding radiological sampling location maps submitted with the Annual Radiological Environmental Operating Report.

21. Inclusion of Specification 6.9.1.9 to revise the schedular requirements for submittal of the Radial Peaking Factor Limit Report. For Unit 2, revise B3/4.2.3 to reference 6.9.1.9.

22. Revision of Section 6.10.1 to change "REPORTABLE OCCURRENCES" to "REPORTABLE EVENTS", to delete the five year record storage requirement for reactor tests and experiments and to provide editorial corrections.

23. Revision of Section 6.10.2 to reflect the succession of the Nuclear Review Board by the Offsite Safety Review staff and to provide editorial corrections.

24. Addition of a footnote to Sections 6.12.1 and 6.12.2 to define radiation intensity as it is used to determine whether an area is a High Radiation Area. 6.12.1 is also revised to delete reference to "Health Physicist" and to provide editorial corrections. 6.12.2 is being revised to reflect the "Senior Nuclear Shift Supervisor" title.

Also revise Section 6.12.1 to reference 10CFR20.203(c) (4), which allows a high radiation area established for thirty days or less to be controlled via direct surveillance.

25. Revision of Section 6.15.1 to change "FSAR" to "UFSAR" and to provide editorial corrections.

26. (Unit 1 only). Revision of Section 6.16 to delete references to past deadlines for Environmental Qualification compliance.

II. Reason for the Proposed Change License Change Request (LCR) 84-01 was initially submitted to the NRC on March 27, 1984, in response to the revised reporting requirements of Generic Letter~a-3-4-3-.-Rev-is-ion-l_to_LCR 84-01 was subsequently submitted on October 6, 1986 and added~c~h~a~n-g~e=s~~~~~

to reflect organizational changes, reflect revised primary coolant specific activity reporting requirements of Generic Letter 85-19 and to provide editorial corrections to the

Technical Specifications. This LCR (i.e., Revision 2) is being NLR-N89050 LCR 84-01 Revision 2 submitted to reflect a recent management reorganization, to propose additional changes to administrative controls and to facilitate NRC review by providing greater description and justification for the changes proposed in the previous revisions.

Reasons for the specific changes listed above, excluding editorial changes, are as follows:

1. "REPORTABLE EVENT" is phraseology consistent with Generic Letter 83-43 and 10CFR50.73.

2. The correct multiplier for the peaking factor relationship is 0.3, which was approved per Amendment 6 to the Salem Unit 2 Technical Specifications. 11 0.3 11 was handwritten into the Technical Specifications; this LCR is typing 11 0.3 11 into the appropriate place. Proposed Specification 6.9.1.9 is the appropriate reference regarding the Radial Peaking Factor Limit Report.

3. Due to the implementation of the LER rule (Generic Letter 83-43), Specification 6.9.1.9.b no longer pertains to thirty-day written reports. Therefore, the references to this Specification are being deleted.

4. Due to improved fuel design, fuel management and the reporting requirements of 10CFR50.72(b) (1) (ii), the NRC has modified the primary coolant specific activity Technical Specification requirements. Generic Letter 85-19 provides guidance in this regard and has been used as a model for the applicable proposed revisions in this LCR.

5. The phrase "in lieu of a Licensee Event Report" is superfluous and its removal is consistent with Generic Letter 83-43. since Specification 3.11.2.4 applies at all times, Specification 3.0.3 is not applicable to it.

6. The changes are consistent with NUREG 0472, "Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors," Revision 3, draft. The current values of allowable activity levels for tritium and I-131 are based on 40CFR141 limits for drinking water pathways. Where such pathways are not potentially affected, it is proposed that the limits be increased.

Cesium-136 was inadvertently included in table 4.12-1, instead of Cs-134, which is the correct isotope per NUREG 0472. An editorial change is being made accordingly.

NLR-N89050 LCR 84-01 Revision 2

7. In the current organization, the General Manager -

Quality Assurance and Nuclear Safety Review has replaced the General Manager - Nuclear Safety Review with regard to responsibility for the Onsite and Offsite Safety Review Groups. This License Change Request proposes changing the title to "General Manager - Quality Assurance and Nuclear Safety" to more accurately reflect the responsibilities of the position (i.e., safety related review and audit functions).

8. "Radiation protection technician*i is the title consistent with the current organizational configuration, not "Health physics technician".

"Radiation protection technician" is being added to table 6.2-1 to be consistent with the current requirement (Specification 6.2.2.c) to have a technician present whenever fuel is in the reactor. Specification 6.2.2.c is being deleted to eliminate redundancy to revised table 6.2-1.

9. The Shift Technical Advisors' reporting responsibility is to the Senior Nuclear Shift Supervisor. The Radiation Protection/Chemistry Manager, as well as the Radiation Protection Engineer, is required to meet or exceed the personnel qualifications criteria of Regulatory Guide 1.8. Responsibility for Fire Brigade training has been transferred from Manager - Nuclear Training to Manager - Site Protection to consolidate administration of the Fire Protection Program.

Appendix A to 10 CFR Part 55 has been deleted. The requirements for the operator requalification program formerly contained in 10CFR55 Appendix A are now contained in 10CFR55.59. The proposed change references the applicable requirements (i.e., 10 CFR Part 55) and reduces the likelihood of requiring an additional Technical Specification change by not being too specific. Operator requalification is still performed in accordance with the NRC-approved requalification program.

10. The title "Assistant General Manager - Salem Operations" position has been deleted in the recent reorganization.

Other changes to the SORC composition are being made to assure that SORC meetings provide for equitable representation of the Salem station departments. By placing restrictions on the use of alternate members and quorum composition, the proposed change will require that at least three departments are represented in the voting quorum for any given SORC meeting .

NLR-N89050 LCR 84-01 Revision 2

11. The SORC responsibilities of Specification 6.5.1.6 are being revised to delete references to internal distribution of reports, which is addressed more appropriately in other sections. For example, Specification 6.5.1.9 addresses distribution of SORC meeting minutes to the General Manager - QA and Nuclear Safety Review and to the Vice President and Chief Nuclear Officer; 6.5.2 addresses the Nuclear Safety Department's review responsibilities; 6.5.3 addresses review and control of activities in general. Therefore, references to SORC interfaces with other Nuclear Department entities are being removed from Specification 6.5.1.6.

Specifications 6.5.1.6(a) and 6.5.3.2(d) are being revised to reflect PSE&G's intention to discontinue use of the significant safety issue determination in favor of consolidating the procedure revision screening and review process under the requirements of 10CFR50.59.

Current Specifications 6.5.1.6(k) and 6.5.1.6(1) require SORC review of all changes to the Emergency Plan and Fire Protection Program Plan, respectively, and their implementing procedures. The proposed change is intended to waive SORC review if the revisions are not safety significant. This will eliminate unnecessary SORC reviews of revisions that are editorial or are otherwise insignificant with respect to safety.

12. Section 6.5.2 currently describes the Onsite Safety Review Group (SRG) as consisting of the Manager - Onsite Safety Review and four dedicated, full time engineers.

Since the SRG actually consists of the Onsite Safety Review Engineer and three dedicated, full time engineers, PSE&G recently received an NRC violation for changing the SRG without prior Commission approval (Inspection Report 50-272/89-03, 50-311/89-03).

The Onsite Safety Review Engineer currently has review as well as management responsibilities within the Onsite Safety Review Group (SRG), thereby justifying, in part, a reduction in SRG staffing level. However, PSE&G is proposing to replace the position of Manager - Offsite Safety Review with that of Manager - Nuclear Safety, who will have management responsibility for both the Onsite Safety Review Group (SRG) and the Offsite Safety Review staff (OSR). In this proposed configuration the SRG and OSR staff will each consist of at least four full time dedicated engineers.

13. The revision to Specification 6.5.2.3 provides more NLR-N89050 LCR 84-01 Revision 2 flexibility to the Nuclear Safety Department with regard to the use of outside consultants/experts. Per Specification 6.5.2.2, reviewers from organizations external to the Nuclear Safety Department are required to meet the same qualification requirements as the OSR staff.

The miscellaneous activities at the end of Specification 6.5.2.4.1 are actually the responsibility of the Onsite Safety Review Group. Since 6.5.2.4.1 pertains to the OSR staff, those activities are being deleted.

Specification 6.5.2.4.2(g) is being revised to indicate that OSR review of anticipated deficiencies includes aspects of design or operation that may not necessarily be classified as safety related but may still affect nuclear safety.

14. The revision to Specification 6.5.2.4.3(i) provides more specific information regarding the personnel who perform the fire protection audits.

15. The record requirements currently described for Nuclear Safety Review are relevant to Offsite Safety Review activities in particular. Relaxing the time constraints for internal distribution of the results of reviews performed per Specification 6.5.2.4 and audit reports performed by consultants will provide schedular flexibility in report preparation without compromising management oversight of the audit and review process.

16. "NSR" is being replaced by "the OSR staff" in Section 6.5.3 because the 10CFR50.59 review activities described therein are performed specifically by the Offsite Safety Review (OSR) staff, which is part of the Nuclear Safety Department.

17. The changes are administrative in nature and are consistent with Generic Letter 83-43 where applicable.

References to the initial submittal of the Annual report are being deleted since the reports have already been submitted for each Salem unit.

18. See change number 4 above. High primary coolant specific activity is no longer classified as a REPORTABLE OCCURRENCE; it will be reported on an annual basis consistent with Generic Letter 85-19.

19. 10CFR50.73(g) states that "The requirements contained in this section replace all existing requirements for Licensees to report REPORTABLE OCCURRENCES as defined in NLR-N89050 LCR 84-01 Revision 2 individual plant Technical Specifications." Therefore, since Specifications 6.9.1.7, 6.9.1.8 and 6.9.1.9 are superceded, they are being deleted.

20. This revision provides more specific information on radiological sampling location maps. Dedicating one map to locations near the site boundary and another to include all locations assures that the maps will be scaled such that they are legible. This change also provides an editorial correction by deleting a footnote that was inadvertently included in Specification 6.9.1.7.

21. The Radial Peaking Factor (F ) Limit Report is currently required to be subffiKtted to the NRC sixty days prior to the date the limit would become effective. In order to provide schedular flexibility in the fuel cycle licensing process, this change proposes allowing report submittal thirty days after the limit has become effective.

Surveil.lances performed on Fx confirm the acceptability of.the corresponding heat flu~ hot channel factor (F 0 )

values. The F limits are determined prior to restart (i.e., in conjfi~ction with the Reload Safety Evaluation). Furthermore, since the report is submitted on an information only basis and not for NRC approval, changing the reporting schedule constitutes a purely administrative change.

22. "Reportable Event" is phraseology consistent with Generic Letter 83-43 and 10CFR50.73.

Currently, records of reactor tests and experiments are addressed in both Section 6.10.l and 6.10.2. Removing it from Section 6.10.1 eliminates redundancy and does not lessen the record storage commitment.

23. "OSR" is the applicable group in the current organizational configuration; the Nuclear Review Board no longer exists.

24. Basing an area's radiation level on measurement 18 inches from the radiation source provides a uniform means of measurement consistent with that of the Hope Creek station. "Radiation Protection" personnel and "Senior Nuclear Shift Supervisor" are the applicable titles in the current organizational configuration.

When a high radiation area is established for a short period of time (i.e., 30 days or less), it is often more NLR-N89050 LCR 84-01 Revision 2 practical to control the area using direct surveillance than to erect a barricade surrounding the area. This approach is consistent with 10CFR20.203(c) (4).

25. "Updated Final Safety Analysis Report" (UFSAR) is the document relevant to Section 6.15.1.

26. Salem Unit l's compliance with Environmental Qualification commitments is documented via docketed correspondence, and references to past deadlines for compliance are not necessary.

III. Justification for the Proposed Change The changes proposed in this LCR may be categorized and justified as follows:

a. Changes to comply with Generic Letter 83-43 (item nos.

1,3,5,17,19,22). These changes are consistent with the guidance provided in the Generic Letter. They are intended to reflect compliance with the universally adopted reporting requirements of 10CFR50.72 and 10CFR50.73, and are administrative in nature *

b. Changes related to PSE&G's organizational configuration, which reflect titular changes, changes in management responsibility, changes to the SORC and those which supplement LCR 88-07 (item nos. 7,8,9,10,ll,12,16,23).

This category is administrative in nature and does not adversely impact management attentiveness to safe operation of the Salem Generating Station. The recent reorganization of PSE&G's Nuclear Department is intended to increase overall management effectiveness, in some cases by consolidating oversight of related activities.

For example, fire brigade training and implementation of the fire protection pr~gram in general will now be administered by the same manager. Also, quality assurance and nuclear safety review and audit activities will both be under the direction of one general manager.

The Manager - Nuclear Safety will assume management responsibility of the Onsite Safety Review staff, thereby allowing the Onsite Safety Review Engineer to dedicate his efforts to review activities.

The changes to SORC composition and voting quorum requirements will increase the level of assurance that the various Station departments are adequately represented in the SORC quorum. By placing a two vote

per department limit on the quorum and restricting the NLR-N89050 LCR 84-01 Revision 2 use of alternates, at least three departments will comprise the quorum of each SORC meeting.

This category includes the proposed change to require SORC review for procedure changes and changes to the Emergency Plan and Fire Protection Program Plan only if a 10CFR50.59 safety evaluation is involved. This approach will consolidate the screening and review process for procedure changes by doing away with the significant safety issue determination currently in use at the Salem Generating Station. Screening for safety significance will be performed by determining 10CFR50.59 applicability (and 10CFR50.54(q) for Emergency Plan changes), which is consistent with NRC regulations regarding procedure changes (10CFR50.59 and 10CFR50.54).

c. Changes consistent with Generic Letter 85-19, which help streamline reporting requirements by allowing high primary coolant activity to be reported annually rather than on a short term basis (item nos. 4,18). This category is consistent with the model Technical Specifications appended to Generic Letter 85-19.

d. Change in the schedule for submitting the Radial Peaking Factor Limit Report (F ), which would prevent the report from becoming ax~onstraint on the restart schedule without affecting the development of the F limits or their use in assuring that F 0 provides th~y margin of safety required by the reloao safety evaluation (item nos. 2,21). A precedent for this change has been set via an amendment issued on the Shearon Harris docket (50-400) on August 16, 1988.

e. Changes related to Radiation Protection and Radiological Monitoring (item nos. 6,20,24). PSE&G's current practice of preparing and submitting the Annual Radiological Environmental Operating Report includes the two sampling location maps explicitly described by the proposed change. This LCR clarifies the current practice, which is acceptable -to the NRC, in order to remove any ambiguity from the Technical Specifications.

Radiation measurement will be made at 18 inches from the source in order to utilize a consistent means for defining a radiation area, high radiation area, etc.

This approach is currently used at the Hope Creek Generating Station and is based on the minimum expected distance between the radiation source and the radiation worker, excluding extremities. Consistent with the practices used to keep exposures ALARA, identification

of hot spots, shielding and minimization of exposure NLR-N89050 LCR 84-01 Revision 2

time (especially at close distances) are used to reduce undue exposures.

The change to the method of preventing unauthorized access to high radiation areas established for thirty days or less is in direct compliance with 10CFR20.203(c) (4). The change is being requested in order to address those cases where it is more feasible to use direct surveillance, instead of a physical barrier, to provide access control.

Changes to reporting levels of radioactivity concentrations and lower limits of detection for the radiological environmental monitoring program are consistent with NUREG 0472, "Standard Radiological Environmental Technical Specifications for Pressurized Water Reactors", Revision 3, draft These changes propose allowing higher levels of tritium and I-131 if a drinking water pathway is not potentially affected by the effluent being monitored. The provisions of 40CFR141 will still be complied with where applicable.

f. Changes to the description of Nuclear Safety Review (NSR) responsibilities (item nos. 12,13,14,15,16).

These changes include consolidating the management of the Offsite and onsite Safety Review Groups and revising the description of NSR activities to increase specificity and eliminate redundancy, and relaxing schedular constraints for internal distribution of audit reports. Changes in this category will not lessen the scope of NSR activities and will increase the effectiveness of the onsite Safety Review Group by allowing the Onsite Safety Review Engineer to dedicate his time to review activities, since the Manager -

Nuclear Safety will have management responsibility. None of the changes in this category will reduce the effectiveness of NSR review and audit functions. The relaxation of schedular requirements for internal distribution of audit reports will increase the time allotted for report preparation and review. Management oversight of the audit process will not be reduced, especially since any potentially significant findings requiring immediate attention may be brought to the attention of the Vice President and Chief Nuclear Officer prior to formal issuance of the audit report.

g. Changes deleting references to past deadlines and outdated requirements or documents are justified on the basis that they are largely editorial and provide clarification without reducing any commitments (item

nos . 9 , 1 7 , 2 5 , 2 6) .

NLR-N89050 LCR 84-01 Revision 2 IV. Significant Hazards Analysis Consideration The proposed changes to the Technical Specifications:

1. Do not involve a significant increase in the probability or consequences of an accident previously evaluated.

Those proposed changes which are administrative in nature do not impact any accident analyses used to support operation of the Salem Nuclear Generating Stations. Furthermore, the proposed changes do not involve any reduction in management effectiveness, nor do they adversely affect the design or operation of any systems or components important to safety.

Consequently, the reliability of the performance of plant safety functions is not adversely affected.

The proposed changes to Section 3.4.8 of Unit 1 and 3.4.9 of Unit 2 delete the action statement requiring discontinuation of operation if primary coolant specific activity exceeds 1.0 µCi/g for 800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months (or 10% of unit total annual operating time) during any 12 mQnth period.

The activity limits of Figure 3.4-1 and 100/E µCi/g will still apply. These limits are bounded by the assumptions used in the steam generator tube rupture accident analysis described in UFSAR Section 15.4.4, which bases primary coolant activity on 1% defective fuel cladding. Therefore, the Technical Specifications will continue to assure that the 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months exclusion area dose in the event of a steam generator tube rupture accident analysis would be a small fraction of the 10CFRlOO limits.

Furthermore, deletion of the 800 hour0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months limit has been endorsed by the NRC in Generic Letter 85-19. The NRC's position is predicated on promulgation of 10CFR50.73 reporting requirements and improvements made in fuel management subsequent to initial development of the primary coolant specific activity limits. Generic Letter 85-19 states that "[l]icensees are expected to continue to monitor activity in the primary coolant and ..* maintain it at a reasonably low level (i.e., accumulated time with high iodine activity should not approach 800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months )". PSE&G recognizes the significance of coolant activity and will continue to monitor and control accumulated specific activity levels.

The proposed increases to the reporting levels of radioactivity and lower limits of detection for tritium and I-131 (Section 3/4.12) do not increase the probability or consequences of an accident. Since the current values are NLR-N89050 LCR 84-01 Revision 2 based on 40CFR141 requirements for drinking water supplies, this proposed change revises those levels in cases where no drinking water pathways are potentially affected. The radiological environmental monitoring program will continue to implement Section IV.B to 10CFR50, Appendix I.

Therefore, it may be concluded that the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Do not create the possibility of a new or different kind of accident from any accident previously evaluated.

The proposed changes do not adversely affect the design or operation of any systems or components important to safety.

No physical plant modifications or new operational configurations will result from these proposed changes.

Therefore, it may be concluded that the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. Do not involve a significant reduction in a margin of safety.

With the exception of the deletion of the 800 hour0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months limit on primary coolant specific activity and revision of radiological environmental monitoring parameters discussed in Section IV.1 above, the changes propose herein potentially affecting parameters defining margins of safety affect only their administrative aspects and do not allow for any reduction in a margin of safety. For example, the proposed changes to Specification 6.9.1.9 regarding F reporting requirements will not reduce the margin of §Kfety associated with the heat flux hot channel factor (F 0 ), since the same methodology will be used to define the acc~ptable limits.

The proposed change to specific activity limits do not involve a significant reduction in a margin of safety. The limits of Figure 3.4-1, which are bounded by the assumption of 1% defective fuel clad for the steam generator tube rupture accident analysis, will still apply. Also, the change has been endorsed by the NRC via Generic Letter 85-19.

The proposed change to the radiological environmental monitoring program do not involve a significant reduction in a margin of safety. The program will still implement Section IV.B to 10CFR50, Appendix I. The proposed change deletes radioactivity concentration values associated with 40CFR141 in cases where it is not applicable (i.e., no NLR-N89050 LCR 84-01 Revision 2 drinking water pathways are involved). Therefore, it may be concluded that the proposed changes do not involve a significant reduction in a margin of safety.

v. Conclusions As discussed above, PSE&G has concluded that the proposed changes to the Technical Specifications do not involve a significant hazards consideration since the changes (i) do not involve a significant increase in the probability or consequences of an accident previously evaluated, (ii) do not create the possibility of a new or different kind of accident from any accident previously evaluated, and (iii) do not involve a significant reduction in a margin of safety.

UNIT 1 MARKUP PAGES INDEX DEFINITIONS SECTION PAGE l.O DEFINITIONS DEFINED TERMS * * * * * * * * * *

1-l ACTION * * * * * * * * * * * * * * * * * * * * * * *

l-1 AXIAL FLUX DIFFERENCE * * **

CHANNEL CALIBRATION **

CH~NEL CHECK * * * * * *

1-1 1-1 1-1 CHANNEL FUNCTIONAL TEST CONTAINMENT INTEGRITY * * * * * * * ***

. . . . . . .. .. l-1 1-2 CONTROLLED LEAKAGE * *

CORE ALTERATION *****

.. ... .. .. .. 1-2 1-2 DOSE EQUIVALENT I-131 * * * * * * * * * * * *

1-2

!-AVERAGE DISINTEGRATION ENERGY ******** 1-3 ENGINEERED SAFETY FEATURE RESPONSE TIME FREQUENCY NOTATION * * * * * * * * * **

... l-3 1-3 GASEOUS RAOWASTE TREATMENT SYSTEM *** 1-3 f IDENTIFIED L£AKAGE * * * * * * * * * * * * * * * * * *

1-3 MEMBER(S) OF THE PUBLIC ** ~ *******

OFFSITE COSE CALCULATION MANUAL (ODCM) **

1-4 1-4

(

OPERABLE

OPERABILITY * * * * * * * * * * * *

1-4 OPERATIONAL MOOE * * * * * * * *

PHYSICS TESTS * * * * * * *

PRESSURE BOUNDARY LEAKAGE. * *

. .. .. . . 1-4 1-5 1*5 (

PROCESS CONTROL PROGRAM (PCP) * * * * * * * * *

1-5 PURGE-PURGING * * * * * * * * * * * * * * * ~ * * * *

1-5 .

QUADRANT POWER TILT RATIO * * * ****** 1-5 RATED THERMAL POWER * * * * * * * * * * * * * * * * *

1-5 REACTOR TRIP SYSTEM RESPONSE TIME **** 1-6 REPORTABLE::tf:CBRRENe~. * * *

1-6 i:i r SHUTDOWH MARGIN. * * * * * ** 1-6 I/

SITE BOUNDARY * * * * * * * * * *

SOLIDIFICATION * * * * * * * ***

SOURCE CHECX * * * * * * * * * * * * * * * * * *

STAGGERED TEST BASIS **** 1-6 THERMAL POWER * * * * * * * * * * * * *

1*7 UNIDENTIFIED LEAKAGE * * * * * ***

UNRESTRICTED AREA * * * . * . * * * * *

. *. . . 1-7 1-7 VENTILATION EXHAUST TREATMENT SYSTEM * * * * * * * * *

1-7 VENTING * . . . * * * * . * * * * * * . 1-7 fl-SALEM - UNIT l Amendment No. <§}

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY 6-1 6.2 ORGANIZATION Onsite and Offsite Organizations 6-1 Facility Staff . . . . . . . . 6-1 Shift Technical Advisor 6-~ 7 6.3 FACILITY STAFF QUALIFICATIONS 6-f 7 6.4 TRAINING . . . . 6-p 7 6.5 REVIEW AND AUDIT 6.5.1 STATION OPERATIONS REVIEW COMMITTEE Function . . . . 6-i g Composition . . . 6-tfJ Alternates 6-19 Meeting Frequency 6-/f fl Quorum . . . . . 6-if ~

Responsibilities 6-;!9

~Review Process . 6-il 10

___ Authority . . . . 6-s! 10 C'Fd ~P'l!iJ RecordSJ.. . . . . 6-d 10 6.5.2 NUCLEAR SAFETY REVIEW Function . . . . . . 6-;1 /0 Composition . . . . . 6'-/5 10 Consultants . . . . . 6-~ //

Off-Site Review ~ ~0 S.R..) 6-'8- I/

evi ew . . . . . . . . . . 6-9-a: I;)..

ud its . . . . . . . . . . . . . 6-16' /~

On-Site Safety: Review Group ~12~). 6-..H' 13 Responsibilities 6-.H I~

Authority . 6-)d" It/

SALEM - UNIT 1 XVIII Amendment No.

INDEX ADMINISTRATIVE CONTROLS

=============================================================

SECTION PAGE 6.5.3 TECHNICAL REVIEW AND CONTROL . 6-H 15' 6.6 REPORTABLE EVENT ACTION . 6-~ 15" 6.7 SAFETY LIMIT VIOLATION

6-:l:-2'D 16 6.8 PROCEDURES AND PROGRAMS . 6-M IC 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS

6-:J..6' 19 6.9.2 SPECIAL REPORTS 6-:.M'" ;;;13 6.10 RECORD RETENTION ... 6-2! ";;l 3 6.11 RADIATION PROTECTION PROGRAM 6.12 HIGH RADIATION AREA . .

6.13 PROCESS CONTROL PROGRAM . 6-;.l4' i:u; 6.14 OFFSITE DOSE CALCULATION MANUAL . . . 6-K ;;;7 6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 6 --2'5" ;l 7 6.16 ENVIRONMENTAL QUALIFICATION . 6-U' -;;) ?

SALEM - UNIT 1 XIX Amendment No.

OVINtTtONS

~E,\CiOR ~t? SYS'iiM ltS~OMSE i!M£ l.Z9 nte REACTOR ilU? SYST'£?4 ~ESPOMSC: i!M! sn*11 t:le Che Chte lneerv*t f.-om .l'!en cne tftQnitart~ ~*r!llleC1r t.1c1eds tes tri~ sec~atnc *C tne ~~innet se~sor ~ntil less af scic1aft*l7 gr1~;1r ca11 volt19*.

f;'l/£N"'" ~OQRl'AIL! <<UiH~

~ l.%7 A "li'OJl'A8L!':il<<aJllEHfllSn111 t:le *'"1 cf thasa cQftct1t1ons s;e<Hfld tn fO,t=HtQlilM 5 ; t.I ll!G l,f,l.W' _.{f_ec.flo11 .f"O. 73 to !DC.FR R;_~f SO)

SHU~N ~.UGI~

l.ZI Si4U~O\Ut 1'.AAGt~ sn111 ~ tn* instviunec"s .aun-t of t"Hc:thtty 0y 'tlffttcn cne rt*ccor ts syOcrtt1~1 or -ould ~* suOcr1tf~1 fl"all tts ;resent cand1t1Qn

ssus1n9 111 1"1111 ltftftl't l"C4 i:lust1r 1ss8110lf1s (s~tda-ft *nd c=ncrol) *~ fully tl'tH~ld t.1i:aat fo:.* cne stngl1 l"04 cluster uu11t1l1 af l'lfgnest rt*cthicy -al"":l't

..,.;~ ts us~ e; ~ ful11 *itndl"a*n.

sr~ 9aulf0.&a?

L.%9 ii!* sti! iC\IMD.&A'f shall 09 t:11t ltne 0.1cnd wn1c:' '!:!* 11nct 1s ,,ac Qlwnt~.

ltHH .* QI" otl't*~1se CQftCl"OllM ~ tJ't* lfctnSff, H Sl'IC'llft fn Ftgure !.l-l, iftd

...,,;en ~ff,,., :n* UC 1us1 Oft .,.... u Sll°"'9 f,, , t ~" 5. 1-1.

~.la SCLtO:~t~rtON sn111 "9 Cite can~*,.,1an ot ...i rtdio*ciive ~seas f~~= *

'Q~ c~1~ ~~s s"1coin9 ift4 ~uri1l ireutid r~irllllftts.

SCURC! CH!CX

l .ll SOURCE OIECX s"1ll b* en. ~il 1Uth* HSHSlll8nt of cn*,,n*l 1"9SCOftH .. ,,.,,

~* ~,*nnel sense~ ts uoasaa co 1 SQ\lrcl Qf fncrt1s~ r141Q1ctivicy.

S~lGU.,~£0 rc:sr !AStS LlZ J. STAGGDID i'EST !Ast S sl't~;ns h~ ot:

a. ~:es~ sc.,Hult 'or ~llllS, suosys~111t. :r1t~s.

~:maanen~s oc~1t~ld Oy d1v;d1ng c"' soe<i't~ c1s~

~u*I s~atn~1rv1ls,

-~-------

rnsT~UMENTAT!ON RADIOACTIVE LIQUID EFFLUENT MONITORING !~STRUMENTATION LIMITING CONOITIO.l rOR OPERATION 3.3.3.8 The radioactive liquid effluent monitoring fnstrumentatfon channels shown in Table 3.3-12 shall be OPERABLE with their alann/tr1p setpoints set to ensure that the limits of Specification 3.ll.l.l are not exceeded. The alann/trip setpoints of these _channels shall be determined in accordance with the OFFSITE DOSE CALCULATION 1~NUAL (OOCM).

APPLICABILITY: At all times.

ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specif1ication, without delay suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable or change the setpoint so ft is acceptably conservative.

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation *channels OPERABLE, take the ACTION shown in Table 3.3-12. Exert best efforts to return the instrt.iment to operable status within 30 days and, if unsuccessful, explain in the next semi-annual radioactive efflu1nt release report why the fnoperability was not corrected in a timely manner.

c. The provisions of Specifications 3.0.3~ ~9.l.9:i> are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.8 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECX, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-12.

~

SAL:'.M - UNIT 1 3/4 3-Sa Amendment Na. & .

INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDlTION FOR OPERATION 3.3.3.9 The radioactive gaseous effluent r.t>nitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with the

~ODCM~

APPLICABILITY: As shown in TablP. 3.3-13 ACTION:

a. With a radioactive gaseous effluent monitoring

instrumentation channel alarm/trip setpoint less conservative than required by the above specification, without delay suspend the release of radioactive gaseous effluents moni tcred by .the affected channel or dee 1are .

the channel inoperable or change the setpof nt so it is acceptably conservative.

b. With less than the minil!llm number of radioactive gaseous effluent monitoring instrunentation channels OPERABLE, take the ACTION shown in Table 3.3-13. Exert best efforts to return the instrument to operable status within 30 days and, if unsuccessful, explain in the next semi-annual rartioactive effluent release report why the inoperability was no~ corrected in a timely manner.

c. The provisions of Specifications 3.0.3~~

t;.9.1.9,&" are not applicable.* r SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive gaseous effluent l!l)nitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, ANO CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-13.

~-

SALEM - UN IT 1 3/4 3-64 Amendm.ent No. <!j

REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant shall be limited to:

a. < 1.0 ~Ci/gram DOSE EQUIVALENT I-131, and

b. ~ 100/r 1.1Ci/gramr--(f8""1;-cz--;;;f,;;hJBU APPLICABILITY: MODES l, 2, 3, 4 and 5 ACTION:

MODES l, 2 and 3~

~:-:-,:-:.t~h-~th_e_S_f3e-e-:i-:.,.-:ie-a-e~ti:-\-:'i~t)-'-0-::f:--*~tA~.e-j:i-!'i-:-11-1&_r_y_r._.FJ_lJ:-1e-~il-:t-*->~l=-.-=g,---,lJC,...,i~/-§-F~

DOSE EQUIW1,LEN1 I 131 b~t witRiA tlie a11e*.::.tl1e limit (bc1e~: /

. and tr:r the 1eft <:Jf the liAe) sAetcA eA rigl:il"'!.. 3.4 1; o~e1*atieA /

may eoRtiRije for yp ta 49 ~eyrs previ-ed that operatioR ijRder /

these ei rc1:1111staAees sl=tal l Aot exeeea 1O pe,*eeAt of tl'1e ufli t' s /

total yearly a~eratiRg time. n1e previsiORS of Spet:ifieatieA) 3.0.4 are Aot applieasle:/,,---

e:H.&-.

With the specif.ic activity of the primc:ry coolant> 1.0 1.1Ci/gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one con-tinuous time interval or exceeding the limit line shewn on Figure 3.4-1, be in al least HOT STANDBY with Tavg < 500°F w.i thin 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

~if. With the specific activity of the primary coolant > 100/t

~Ci/gram, be in at least HOT STANDBY with Tavg < 500°F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

MODES l, 2, 3, 4 and 5

a. With the specific activity of the primary coolant> 1.0 uCi/gram DOSE EQUIVALENT I-131 or> 100/t 1.1Ci/gram, perform the sampling and analysis requirements of item 4a of Table 4.4-2 until the

~~~~=~~;!~:~!:~~!~::~t~~;~~~i~~~

With Tavg -> 500 6 F*

.SALEM - UNIT 1 3/4 4-20

REACTOR COOLANT SYSTEM

1. Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first samp1e in which the limit was exceeded,

2. Fuel burnup by core region,

3. Glean up flo~ history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . prior to tne---f-i-l"S-t:

sample in which the limit was exceeded,

4. History of de gassing operations, if any, starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months pri~r to the first sample in which the 1imit was exceeded,

. -a-Rd . . : . . . ~.... ~ .

5. T.he tini~ duration when the specific activity of the

..\

. . .. . . ... ~,. : ..

1%":;., SURVEILLANCE REQUIRFMt.rrt's ...

1.*. :-

4.4.. 8 ~-The sp~cific activity of the pdrnary coolant shall be determined to be w~.thin:-.the:Umits by performance of the sampling and analysis program _(if:T?-t}i_e *.f. 4-*4. .. .,. **

SALEM - UNIT l 3/4 4-21

RADIOACTIVE EFFLUENTS QQg_

LIMITING CONDITION FOR OPERATION 3.11.1.2 The.dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materiaJs in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS (see.Figure 5.1-3) shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, and

. b. During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, (If 11eH ef~

Mieeffie E..,eet ReW'Q prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause{s) for exceeding the limit{s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11~1.2 Cumulative dose contributions from liquid effluents shall be determined in accordance with the ODCM at least once per 31 days.

SALEM - UNIT 1 3/4 ll-5 Amendment No. @'2

RADIOACTIVE EFFLUENTS LIQUID RAOWASTE TREATMEN~

LIMITING CONDITION 'FOR OPERATION 3.ll.l.3 The liquid radwaste treatment system shall be used to reduce the radioactive materials 11qu1d wastes prior to their discharge when the projected cumulative doses due to the liquid effluent from each reactor to UNRESTRICTED AREAS (see Figure 5.1-3) exceed 0.375 mrem to the total body or 1.25 mrem to any organ during any calendar quarter.

APPLICABILITY: At all times.

ACTION:

a. With the radioactive liquid waste being discharged without treatment and in excess of the above limits, <tii 11ew at 1 li01sseu EnMt Repof!;:{-

.prepare and submit to the Corrunission within 30 days, pursuant to Sp~~iffcation 6.9.2 1 a Special Report that includes tlte followihg information:

l. ExpJanation of why liquid radwaste was being discharged .,,.ithout treatment, 1dentif1cation of any inoperable equipment or subsystems, and the reason for the inoperability.

2. Act1on(s) taken to restore the inoperable equipment to OPERABLE status, and

3. Surrunary description of action(s) t_aken to prevent a recurrence.

b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEI!.LANCE REQUIREMENTS 4.ll.l.3 Doses* due to liquid releases shall be projected. at least once per 31 days in accordance with the OOCM.

S.:.L:'.~ - UNIT l 3/4 11-6 Amendment ;'io. ~

RADIOACTIVE EFFLUENTS DOSE

NOSLE GASES LIMITING*CONOITION FOR OPERATION 3.11.2.2 The air dose due to noble ga~es released fn gaseous effluents, from each M!actor unit, from the site areas at and beyond the SITE BOUNDARY (see Figure 5.1*3) shall be limited to*the follO'!lling:

a. Curing any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to lO mrad for beta radiation and,

o. Curing any calendar year: Less than or equal to 10 mrad for 9a1m1a radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILITY: At all times.

ACTION:

a. With the calculated afr dose fran radioactive noble gases in gaseous effluents exceeding any of the above limits, ctri" ~!eii af a LieeA{!~

~est Reaeet& prepare and submit to the Commission within 30 days, pursuant to Specification 5.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions*

that have been taken to reduce the release and the proposed corrective actions to be taken to assure that subsequent releases will be in comQlianc:e with the above limits.

b. The provisions of Specifications .3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REOU!REME:NTS

4. ll.2 .2 Cumulative dose contri bu ti ons for tne current ca 1endar quarter and current calendar year shall be detennined in accordance with the OOC~ at leas~

once per 3l days *

s;.L:.:~ - !J~HT l 3/4 'tl-12 Amendment ~la.~

RADIOACTIVE EFFLUENTS*

DOSE - IOOINE-131, TRITIUM, AND RADIONUCLIOES IN PARTICULATE FORM LIMITING CONDITION FOR OPERATION 3.11.2.3 The.dose to a MEMBER OF THE PUBLIC from 1odine-131, from tritium, and from all radionucl1des in particulate form with half-lives greater than 8 days in gaseous effluents.released, f~an each reactor unit, from the site to areas at and beyond the SITE BOUNDARY (see Fi-gure 5*.1-3) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ and,

b. During any calendar year: Less than or equal to 15 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated~dose from the release of iodine-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days. in gaseous effluents exceeding any of the above limits. <tn:FetP

-9 c-qf a Licensee Event !tef:mrt~ prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that*

identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the release and the proposed corrective actions to be taken to assure that subsequent release~ will be in compliance with the above limits. *

b. The provisions of Specifications 3.0.3 and 3.0.4 are* not applicable.

SURVE'ILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the OOCM .at least once per 31 days.

No.~

SALEM - UNIT 1 3/4 11-13 Amendment

RAOtOACT!VE EFFLUENTS GASEOUS R*AOWASTE TREATMENT LIMITING CONOIT!O~ FOR OPERATION 3.ll.2.4 The GASEOUS RAOWASTE TREATMENT SYSTEM and the VENTILIATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases, from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.l-3~exceed 0.625 mrad for gamma radiation and 1.25 mrad for beta radiation in any calendar quarter. The VENTILIATION EXHAUST TREATMENT SYST"EM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases, from each reactor unit, from the site to areas at and beyond.the SITE BOUNDARY (see Figure .5.l-3) would exceed 1.875 mrem to any organ in any calendar quarter.

APPLICABILITY: At all times.

ACTION:

a. ,,,.ith gaseous waste being discharged without treatment and in excess of the above 1imits, ~Ffl!tEM a*, ftensH "ien-t u'f!£( pr:epare and submit to theConm1ssi_on within 30 days, pursuant to Specification 6.9.2, a Special Report that Jncludes the following information:

l. Explanation of why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the .reason for the inoperability,

2. Action(s) taken to restore the inoperable equipment ~i~m~to OPERABLE status, and

3. Summary description of action{s) taken to prevent a recurrence.

b. The provisions of Specificationsr3.0.4 are not applicable.

(3.0.3 q;o SUR'IEILLANCE REQUIREMENTS 4.ll.2.4 Coses due to gaseous releases from the site shall be projected at lease once per 31 days in accordance with the OOCM.

S).LS~ - UNIT l 3/4 ll-14. *Amendment ~lo. r-

SOLID RADIOACTIVE WASTE LIMITING CONDITION FOR OPERATION 3.11.3. The sol id radwaste syste111 shall be used in accorr:tance with a PROCESS CONTROL PROGRAM to process wet radioactive waste to 1t2et shipping and burial ground require1t2nts.

APPLICABILITY: At all times.

ACTION:

a. With the provisions of the PROCESS CONTROL PROGRAM not satisfied, suspend shipments of defectively processed or defectively packilged solid radioactive . wastes frol"I the site.* - _j2..-

b. The provisions of Specifications 3.0.3 and 3.0.481ja 6,-9.1.~ are mt applicable.

SURVEILLANCE RECUIRE~ENTS

4.11.3. The PROCESS CONTROL PROGRAM shall be used to verify the SOLIDIFICATION of at least one representative test specimen from at least every tenth batch of each type of wet radioactive waste (e.g.~ filter sludges, spen~

evaporator bottoms, boric. acid solutions, and sodiu111 sulfate solutions).

a. If any test specimen fails to verify SOLIDIFICATION, the SOLIDIFICATION.

of the *batch under test shall be suspended until such tirre as additional test specimens can be obta1ned, alternative SOLIDIFICATION para~ters can be deterl"li ned in accordance with the PROCESS CONTROL PROGRAM, and a subsequent test verifies. SOLIDIFICATION. SOLIDIFICATION of the batch "'ay then he resumed using the alternative SOLIDIFCATION

. parameters deterl"li neii by the PROCESS CONTROL PROGRAM.

b. If the initial test specimen from a batch of waste fitils to verify SOLIDIFICATION, the PROCESS CONT~OL PROGRAM shall provide for the co 11 ect ion and testing of repres@ntat i ve test specimens from each consecutive batch of the sa1t2 type of wet waste until at least three consecutive initial test specirrens de1TDnstrate.SOLIDIFICATION. The PROCESS CONTROL PROGRAM shall be POdified as required, as provided in Specification 6.13, to assure SOLIDIFICATION of subsequent batches of waste.

SALEM - UNIT l 3/4 11-17 Amendment No. ~

RAOtOACTtVE EFFLUENTS 3/4.ll.4 TOTAL DOSE LIMITING CONDITION rOR OPERATION 3.ll.4 The annual (calendar year) dose or dose commitment to any MEMBER OF r.~E PUBLIC, due to releases of radioactivity and radiation, from urnaium fuel cycle sources shall be lfmite<i to less than or equal to 25 mrems to the total body or any organ (except the thyroid, which shall be lfm1ted to less than or equal to 75 mr~ms).

APPLICABILITY: At al"l times ACTION:

a. With the calculate<! doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specification 3.l1.l.2a, 3.ll.l.2b, 3.ll.2.2a, 3.ll.2.2b, 3.11.2.Ja, or 3.ll.2.3b,

~alculations should be made including direct radiation contributions from the reactor units and fron outside storage tanKs to determine whether the limits of this Specification have been exceeded. If such is the castrm;--1\elF!._8-=-t;tceosre Event-=lte@Cfr.t>, prepare and submit to_

the Commission withtn 30 days, pursuant to Specification 6.9.2, a Special Report that defines the corrective ai:'tton to be taKen to reduce subsequent rel eases to prevent recurrence o*f exceeding the above 1i mi ts and includes the schedule for achieving confor-mance with the above limits. This Specical RepoM:, as defined in 10 CFR Par-t 20.405c, shall include an analysis that .estimates the radiation exposure (dose) to a

~EMBER OF THE PUBLIC from uranium fuel cycle sources, including all eff1uent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. rf

/~estimated dose(s) exceeds the above limits, and if the release l!J condtion resulting in violation of 40 CFR Part 190 has.not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the repor-t is considered a timely request, and a variance is granted until staff action on the request is complete.

3/4. Ll*l8 Amendment Na~~

3/4.12 RADIOLOGICAL ~NVIRONMENTAL MONITORING 3/4.12.l MONITORING PROGRAM LIMITING CONDITION :FOR OPERATION 3.12.1. The radiological environmental monitoring program shall be conducted as specified in Table 3.12-1.

APPLICABILITY: At all times.

ACTION:

a. With the radiological environmental monitorina program not being _r:z_

. conducted as specified in Table 3.12-l,djj lieu ot-a L1eensee Event)

~.prepare and submit to the Commission, in the Annual

~~ical Environmental Operating Report required by Specification l.!J 0~~~1~~, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, <m:=""'" of a Licensee Event Report:;tprepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2", a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to* a MEMBER OF THE PUBLIC is less than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2, and 3.11.2.3. When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if: *

~oncentration (l) concentration (2)

+ + *** >1.0 reporting level {l) *reporting level (2)

When radionuclides other than those. in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a member of the publi.c is equal to or greater SALEM - UNIT l 3/4 12-1 Amendment No.~

3/4.12 RADIOLOGICAL ENV!RONMENTAL MONITORING 3/4.12.l MONITORING PROGRAM LIMITING CONOIT!ON FOR OPERATION ACTION: (Cont'd) than the calendar year limits of Specifications 3.11.l.2, 3.11.2.2, and 3.ll.2.J. This report 1s not required ff the measured level of radioactivity was not the result of plant. effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.12*1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days. The specific:

locations from which samples ~ere unavailable may then be deleted from the manitorin~ program.

fO+- ~at a Licensee Evenr: Repor~ aAJfursuant to Spec1f1 cation U!' 5.9.L~-. identify the cause oft e unavailability. of samples and the new location(s) for obtaining replacement samples fn the next Semiannual Radioactive Effluent Release Report. Include fn the report a revised figure(s) and table for the OOCM*reflecting the new location(s).

d. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall .be collected pur~uant to Table 3.l2*l from the locations specified in the OOC~ and shall be analyzed pursuant to the requirements of Table 4.12-l.

SAL£~ - U~H T l 3/4 12-2 Amendment '10. if"

c z

-i

-* . REPORTING LEVELS FOR

~12-2 RAOIOACTIVITY~ENTRAflONS Reporting levels~

IN ENVIRONMENTAL SAMPLES Water Airborne Parttculate Fish Htlk Food Products Analysis (pCt/l) or Gases (pCt/ml) (pct /Kg, wet) (pct 11) (pCt/Kg, wet)

~

11-3 2 x 104(y)

Hn-54 l x 101 J x 104 f e-59 4 x 102 l x 104 Co-58 l x .101 J x 104 Co-6() l x 102 1 x 104

.~

N Zn-65 l x *102 2 x 104 I

00 Zr-Nb-95 4 x 102 1- lll 2 o. CJ l l x 102 Cs-134 30 10 1 x 1ol 60 I x 101

);;.o 3

fD

J Cs-137 50 20 2 x 101 70 2 )( 101

~

ID

J Da-La-140 2 x 102 3 )( 102 n

z

'ff."

Thts ts 4Q]:FR~41 value. olr,'r'lift11~

0 (f') for drlnktng water samples. :IF 110 weifer fq,f4wety

Ul

O

.-JCt's fs I Cl vei.fue o-F '.$ ~ Io i/ F C,-/; /r?"< r {J e us ed.-

~------ -

V)

~

,.,r TABLE 4.12-1

~ . ~b MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)

Water Atrborne Parttculate Ftsh Mtlk FOod Products ... Sediment Analysts (pCt/l) or Gases* (pct /ml) (pCt/Kg, wet) (pCt/l) (pCt/Kg *. wet) (pCt/Kg. dry)

!JfOSS beta 4 1 x 10-2 11-l 2oo&V Hn-54* 15 130 Fe-59 30 260 Co-58

60 15 130 N

I Zn-65 30 260

'° Zr-Nf}-95 15 I-Ill 0 1 x 10-2 1 60

);>

Cs-n/~ 15 5 x 10-2 110 15 60 150 3

II>

J Cs-137 18 6 x 10-2 150 18 80 180

~

II>

J. lla-La-140 15 15 rt 2

0 UI lD

TABLE 4.12-l (Cont'd)

TABLE NOTATION a Required detection capabilities for thermaluminescent dosimeters used for environmental measurements are given i~ Regulatory Guide 4.13, Rev. l, July 1977. .

b The LLD is defined in Table 4.ll-l.

c .:r-F no olr~n1t.1nJ <..b.ter ~-fi~r e.K1tfs,. a.. 114fue o-F ::soco p C.* /t

~ t fO e u~ eo/.

C1.

of t..l.D -For Jn111t,;"J. w~f-er- 5c;~p!e>.. I-F /JO c:ir.'11K,',,,j c.A.l--e1 fCf.+ltway e~sfs I if~ LL 0 o-F ;-cuntnct iso-lopr'c. a11a:fr;-;_s mer be u~'1J.

3/4 12-10 Amendment No.~

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LANO USE CENSUS

LIMITING CONDITION FOR OPERATION 3.12.2. A land use census shall be conducted and shall identify within a distance of 8 ~:n (5 m11es) the location ii'! each of the 16 meteoro1ogica1 sectors of the nearest milk animal A the nearest residence and the ~earest garden* of greater tnan 50 m2 (500 ft') producing broad leaf vegetation. (For elevated releases as defined in Regulatory Guide l.lll, Revision l, July 1977, the land use census shall also identify within a distance of 5 km (3 miles) the locations in each of the 16 meteorological sectors of all milk aniriials and all gardens of greater than 50 m2 producing broa~ leaf vegetation. ~

APPLICABILITY: At all times.

ACTION:

a. With a land use census identifying a location(s) that yields a calculated dose or dose cormiitment greater than the values currently being calculated in Specification 4.ll.2.3, c:{ij lfetJ af 1 LOieeAsee E\i~

..,:;z .Alpern identify the new location(s) in the next Semiannual Radioactive*

Effluen~ Release Report, purs*uant to Specification 6.9.l.~

b. With a land use census identifying a location(s) that yields a *

(

calculated dose or dose cOlmlitl!'l!nt (via~the Sall'I! exposure pathway) 20 percent greater than at a locatian from which samples are currently being obtained in accordance with Specification 3.12.l, add the new location(s) to the radiological environl'Tll!ntal r.onitoring program within 30 days. The sa~ling location(s), excluding the control station location, having the lowest calculated oose or oose cormiitment(s) (via the safT1! exposure pathway) may be deleted from this rn:>nitoring program after}'(DJctober 3l~of the year in which this land use census was

_.. conducted. dB Hee et' 1 lirkefl!H Ewell£ Report a8i',$ursuant to

§)-Specification 6.9.l."'M, identify the new location(s) in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure(s) and table for the OQCM reflecting the new location(s).

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

Sroad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted 0/0 in 1 ieu of the garr.len census. Specifications for broadleaf vegetation sampling in Table 3.l2-l.4c shall be followed, including analysis of control samples.

SALEM - UNIT l 3/4 12-11 Amendment No. ?

f

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.LZ.Z LANO USE C~NSUS (Cont'd)

SURVEILLANCE REQUIREMENTS 4.12.2 The land usa census shali be conducted dur1n9 the ;ro~1ns s~dSv~ at 1eas: once per lZ mQn~hs using that infonnation that will provide :he :est results, su'h as by a daor-to-door survey, aerial survey, or by consulting local agricultur.e authorities. The results of tl'le land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Soecif1cation 5.9.l.te-

. .& J S),L~:-4

UNIT l 3/4. tZ-LZ Amendment ~la.&

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3. INTERLABORATORY COMPARISON PROG~AM LIMITING CONDITlON FOR OPERATION 3.12.3 Aria1ysies slia11 be perfoiiiied en rad1oacti*;e m~te:-ials suopl-iad a~ ~:"'~ cf an Interlaboratory Comparison Program *~hich has ceen approv~<j by t:ie Commissic~.

APPLICABILITY: At all times.

ACTION: .

a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.l.~;::'\

b.

-w The provisions of Specifications 3.0.3 and 3.0.4. are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.3 A summary of the results obtained as part of the above required

!nterlaboratory Comparison Program and in accordance with the ODCM shall be

.'d) .

included in the Annual Radiological Environmental Operating Report pursuant to Specif t catton 6. 9. l SALEM - UNIT l 3/4 12-13 Amendment ~lo. ff

REACTOR COOL~'rr S'fS'Th\f BASES 3/4.4. a Sl'!CtF!C ACT!vt'if in* Hnrftlt'fcns on the s12ac1f~c i<.:~~'11-:y o'f tilt ?ritr.ar"J c:otant insure that th* rHult1ng % hour doses at t.ltt s1ta bcundlr"J ...,;n not 1xc!td an appropr'fat!ly small fraction of ?!rt 100 limit.i followin~ a staam generator tuce l"'Uptur-9 ac::ict.nt fn canjunct'f an *..rt th !n uswr.ed staid!' stat.I pr'fmary-tc-secandar"J stHm gentrncr luka;* 1"1t1 of 1.0 GPM. iht val uas for tne limits on Sil.Ci f1 c ac't"t vi ty r9Pr9Silt t 1nt r'! :T:

. limits based upon I ~arimetric 1*11luat1on oy tnt 1'IRC of typ'fcal sit.a locations. i'nua nlues aMI ccns1l"'1at1vt 1n that specific sita ~ar!lft-1tars of tnt Salem si-:a, sucn as sit* boundary location and ir.ata~rologi cal ccnd1t1cns~ w*i-11 not ccnsidal'"ed in th1s 1valu1t1on. rne NRC is f1nali:1ng s1te sptcific o-1tal"1a '"'hich ...,111 bt used as tna basis for the ~valuation of the specific activity limits of ~ltis Sita. 7"nis reevaluation may 1'"9su1t fn h1gntr lfm1ts.

~educing ra ta <SOo*F pr9vents the ~9le!sa of ac~iv1tJ sr.ould a staaaz genera~r ~be r~ptu1"9 since ~~e sa~rat1on ~r~ssur! oi e~e ,r1~ar:

c=olant fs O.low the lift or!ssur! 01 t.~e atinascne~1c s:um 1"'!1 ief *1a~*1es.

i'n* sur"1ei i 1anca ~ui l'"!!!lents pl"'Ovi de !dequau ~sswranca :.:ia t excas si'le s~ecific activity levels in the primary coolant wiil 01 ~*~

suf1icient c1me ta :aka ca~c~ive action. tnforma:ion oo:iiM!<i en iodfne spik1nq ~111 be used to assess the ?arimetars associata~ ~i:.:i spiking ?henc:mena. A r!Cuction in fi-~uency of isot:;:ic ar.al:1ses fol~c*,Jinq

~ewer :~an;as may be permissibie if justified by the data cc:!inee.

3 !/'.:. <l-3

I

6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY

6.1.l The General Manager - Salem Operations shall be responsible for overall facility operation and shall delegate, in writing, the succession to this responsibility during his absence.

6.1.2 The Senior Nuclear Shift Supervisor, or during his absence from the control room a designated individual, shall be responsible for the control room command function. A management directive to this effect, signed by the Vice President and Chief Nuclear Officer, shall be reissued to all station personnel on an annual basis.

6.2 ORGANIZATION 6.2.l ONSITE AND OFFSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include positions for activities affecting the safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shall be established and defined from the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the Salem Updated Final Safety Analysis Report and updated in accordance with 10 CFR 50.7l(e).

b. The General Manager - Salem Operations shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

c. The Vice President and Chief Nuclear Officer shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

d. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

6.2.2 FACILITY STAFF The facility organization shall be subject to the following:

a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1; SALEM - UNIT 1 6-1 Amendment No.

ADMINISTRATIVE CONTROLS FACILITY STAFF (continued) n t

~~ -1.<e~

b. At least one licensedYQPerator shall be in the control room when fuel is in the reactor. In addition, at least one licensed Senior Reactor Operator shall be in the control room area at all times

e. A health physies teehnieiae* shall he ea site whee fuel is ia the reaeter ALL CORE ALTERATIONS shall be observed and directly supervised by a licensed Senior Reactor Operator who has no other concurrent responsibilities during this operation A site Fire Brigade of at least 5 members shall be maintained onsite at all times*. The Fire Brigade shall not include 4 members of the minimum shift crew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency.

£ t. The amount of overtime worked by plant staff members performing safety-related functions must be limited in accord'ance with the NRC Policy Statement on working hours (Generic Letter No. 82-12).

The Operations Manager, Operating Engineer, Senior Nuclear Shift Supervisor, and Nuclear Shift Supervisor shall each hold a senior reactor operator license. The Nuclear Control Operators shall hold

reactor operator licenses.

The health physies teeheieiaa aaa Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of the health physiss teshaisiaa aeG/Qr Fire Brigade members provided immediate action is taken to restore the health physies teehnieian and/or Fire Brigade to within the minimum requirements *

SALEM - UNIT 1 Amendment No.

Figure 6.2-1 CORPORATE HEADQUARTERS AND OFF~SITE ORGANIZATION FOR MANAGEMENT AND TECHNICAL SUPPORT (Deleted) f

SALEM - UN IT 1 Amendment No.

FIGURE 6.2 - 2 FACILITY ORGANIZATION (Deleted)

(

SALEM - UN IT 1 6-j '1 Amendment No.

TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION SALEM UNIT 1

POSITION WITH UNIT 2 IN MODES 5 OR 6 OR DE-FUELED NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION MODES 1, 2' 3 & 4 MODES 5 & 6 (,;

/' '*

SNSS la la SRO lb none STA lb none NCO 2 le EO/UO 3 2 Maintenance Electrician 1 none ka.of. Pro. I ec hnicl4 !:J I a.. I a.,.'!.

WITH UNIT 2 IN MODES 1, 2, ~ OR 4 POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION MODES 1, 2, 3 4 MODES 5 6 x_

SNSS la la SRO lb none STA lb none NCO 2d 1 EO/UO 3 1 Maintenance Electrician la none

({..a.J. Pro. Techfl,"a./e," I CJ- I a...

Individual may fill the same position on Unit 2 Individual who fulfills the STA requirement may fill the same position on Unit 2. The STA, if a licensed SRO, may concurrently fill the SRO position on one unit; the -0ther unit also requires a qualified SRO on shift.

~/ One of the two required individuals may fill the position on Unit 2, such that there are a total of three EO/UO's for both units.

One of the three required individuals may fill the same position of Unit 2, such that there are a total of five EO/UO's for both units.

(

f /ie(!c/(?j .-F /oof!i rea_c.fo1s ofe-F~/ecl.

~1 fl)o q_fe

SALEM - UN IT 1 Amendment No. @

TABLE 6.2-1 (Continued)

SNSS - Senior Nuclear Shift Supervisor with a Senior Reactor Operator License on both units.

SRO - Individual with a Senior Reactor Operator License on both units (normally, a Nuclear Shift Supervisor).

NCO - Nuclear Control Operator with a Reactor Operator License on both units.

STA - Shift Technical Advisor (if licensed as SRO, may be assigned duties as a Nuclear Shift Supervisor).

EO/UO- Equipment Operator or Utility Operator.

Except for the Senior Nuclear Shift Supervisor, the Shift Crew Composition may ~

be one less than the minimum requirements of Table 6.2-1 for a period of time ~

not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate the unexpected absence of .

on-duty shift crew members provided that immediate action is taken to restore the Shift Crew Composition to within the minimum requirements of Table 6.2-1.

This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewperson s being late or absent.

1 During any absence of the Senior Nuclear Shift Supervisor from the Control 1*.

Room area while the unit is in any MODE, an individual with a valid SRO License shall be designated to assume the Control Room command function .

SALEM - UNIT 1 6-f & Amendment No. ~

ADMINISTRATIVE CONTROLS 6.2.3 SHIFT TECHNICAL ADVISOR 6.2.3.1 The Shift Technical Advisor shall serve in an advisory capacity to *

/or r-----

the Shift Supervisor on matters pertaining to the engineering aspects assuring c..leu safe operation of the unit.

6.2.3.2 The Shift Technical Advisor shall have a Bachelor's Degree or equivalent in a scientific or engineering discipline with specific training in plant design and response and analysis of the plant for transients and accidents.

6.3 FACILITY STAFF QUALIFICATIONS 6.3.l Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI Nl8.l-1971 for comparable positions and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRG letter to all licensees, except for the Radiation Protection Engineer who shall meet or exceed the qualifications of Regulatory Guide 1.8, Septemb~e=-..l.;1~9~7~5~*-~---::------:-----,----;------:-~-:A'"----:

or R.a.d,'a. f1l>n frofecf1011 / c/,ern1s+r1 Ariq7er 6 .4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be coordinated by each functional level manager (Department Head) at the facility and maintained under the direction of the Manager - Nuclear Training 10 c.FR.. and shall meet or exceed the requirements and recommendations of Section 5.5 farf S"b of ANSI Nl8.l-1971 and Appe.ru:ii~A!!.-of 10 CFR Part 55 and the supplemental reqJ,,l,inim~ats sp~cified in Sectioas A aad C of li:m:los\u;e l of the Mareh 28,

J:.9-8-0-NRG letter to all lieensees-,-aaG-shall include familiarization with relevant irnl~perational~

6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Manager - Nuelear Training and shall meet or exceed the requirements of Section 27 o]FPA Code-1975, except for Fire.Brigade training sessions which shall be held t least quarterly.

. s;:;_e Pro-lecg .

SALEM - UNIT 1 6-fl Amendment No. 62

- I ADMINISTRATIVE CONTROLS 6.5 REVIEW AND AUDIT

6.5.l FUNCTION STATION OPERATIONS REVIEW COMMITTEE (SORG) 6.5.1.l The Station Operations Review Committee shall function to advise the General Manager - Salem Operations on operational matters related to nuclear safety.

COMPOSITION 6.5.1.2 The Station Operations Review Committee (SORG) shall be composed of:

5:EE :;::tJ<;E{!( TO 6'. t)./,?.

Chairman: General Manager Salem Operatiens Memeer and Vice Chairman: Asst. General Manager Salem Operations Mef!leer B:fid Vice Chairman: Maintenanee MB£lager Member and: Viee ChairmB:n. Operati~ Manager Member and Viee Chairman: Teehnieal Manager Member: Operating Engineer Member: I & C Engineer Member: Senier Nuclear Shift Superviser Member: Teehnieal Engineers ((Froc1f 1-!<<ao&)

MeH1eer: Maintenan~e EngineeI."

Mell!Ger; Radiation Proteetien Engineer MeH1eer: Chemistry Engineer Member: Manager On Site Safety Review Group or his designee.

r()Qpq ~er:

Rauf '4f>"on /11 ar*c i'/u;j r' 6 ~e "I '* .,.T ,"4....1A~e1 ALTERNATES 5e~ "I:t'JS£RT To ~.!)./. 3 6.5.l.3 All alternate members shall be appointed in writing ey the SORG Chairman.

a. Viee Chairmen shall be mell!Gers of Station management

b. No more than twe alternates to members shall partieipate as voting members in SORG aetivities at anv one meetini;z;

c. Alternate appointees will only represent th,lir I."e~pective den ar tment .

d. l'.. lternates for members will not make up part of the voting quoruFll

!When the members the alternate represents is also present.

MEETING FREQUENCY 6.5.1.4 The SORG shall meet at least once per calendar month and as convened by the SORG Chairman or his designated alternate.

QUORUM 6.5.1.5 The minimum quorum of the SORG necessary for the performance of the SORG responsibility and authority provisions of these technical specifications shall consist of the Chairman or his designated alternate and five members

. including alternates. £" .., .,..- .,., L"' - C

>l

E .v/1)$/:;;21 ,o 1::> *5* 1*v SALEM - UNIT 1 6-f'6 Amendment No. 62

INSERT TO SECTION 6.5.1.2 Chairman: General Manager - Salem Operations Member and Vice Chairman: Maintenance Manager Member and Vice Chairman: Operations Manager Member and Vice Chairman: Technical Manager Member: Radiation Protection/Chemistry

Manager Member: Radiation Protection Engineer Member: Chemistry Engineer Member: Maintenance Engineers Member: Operating Engineers Member: Technical Engineers (Group Heads)

Member: Onsite Safety Review Engineer INSERT TO SECTION 6

5. 1. 3.

6.5.1.3 Alternates:

a. Alternates shall be appointed by the SORC Chairman in writing.

. b. Only designated Vice Chairmen may act as Chairman of a SORC meeting in the absence of the General Manager -

Salem Operations.

c. The Senior Nuclear Shift Supervisor (SNSS) may act as an alternate for the Operations Manager or an Operating Engineer. The SNSS may also act as an alternate when the Operations Manager is acting as Chairman.

INSERT TO SECTION 6.5.1.5

a. No more than two members or one member and one alternate from any individual department will make up part of the voting quorum.

b. If the Chairman for a meeting is a Vice Chairman, then up to two additional members (or one member and one alternate) may be part of the voting quorum.

-~I ADMINISTRATIVE CONTROLS RESPONSIBILITIES 6.5.1.6 The Station Operations Review Committee shall be responsible for:

a. Review of: (1) Station Administrative Procedures and changes thereto reiw.;re a.. and (2) Newly created procedures or changes to existing procedures that involve a signifieaRt safety i3stie as described in Section Se<.Fe.fy evcduQ.tio11 6.5.3.2.d.

b. Review of all proposed tests and experiments that affect nuclear safety.

c. Review of all proposed changes to Appendix "A" Technical Specifications.

d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.

e. Review of the safety evaluations that have been completed under the provisions of 10 CFR 50.59.

~nvestigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence. ee:::.:cfie Viee President and Chief Nuclear Offieer and the General Manager -

Nuclear Safety Review.

g. Review of all REPORTABLE EVENTS.

h. Review of facility operations to detect potential nuclear safety hazards.

de+~ur1/t1{Jj ~r i. Performance of special reviews, investigations or analyses and reports thereon as rreeeq~u~e~s~t~e~dr--1b~)~'-tthttec-tG~e~n~e~r~aEr+/-l--+/-"lM~a~n~aHg~e~r~~~s~a~1~e~mri

+t,(2 5oRC. Operations or Gener~aHl-i>M~aHn~a~g~e&ri=-~~N~u~e~lHe~a~ri=-~s~a~f~e~t~)~*~R~e&*~v~i~e~w~.

c ho.111t'$

-rherefo.

j. Review of the Facility Security Plan and implementing procedures an i;.ho.n~es +l.erefo submittal of reeoHlH!ended changes to the General Manager Nuclear f-ht:t+ reiu ire_ Safety Review.

'l 10 c. FR. b0.5 9' St<fe ei1~fut1.f~ k. Review of the Facility Emergency Plan and implementing procedures

~..:.:...::.......<'--~~...--"~~~-a-n-d"::'J.

e.~~~~~~~~~~~o~r~i=n~v~o~v~~~:o-:=po~~en~~~4~/~~e.~~~r.!e~Q~~=e~IU~~r-J,~e:i:=::e~+~h~~~c-T~1~il'-e~-:-~-ss--i oF +~e pku?, per IOC.FR ~t>.S'f(t().

1. Review of the Fire Protection Program and implementing procedures and ~ubmittal of reeoH1IRended changes to the General Manager Nuclear Safety Review,

m. Review of all unplanned on-site releases of radioactivity to the environs including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence. and the forwarding of these reperts to the Vice President and Chief Nuelear Offieer and the General Ma:nager Naclear Safety Review.

SALEM - UNIT 1 Amendment No.

ADMINISTRATIVE CONTROLS RESPONSIBILITIES (continued)

n. Review of changes to the PROCESS CONTROL MANUAL and the OFF-SITE DOSE CALCULATION MANUAL.

SORG REVIEW PROCESS 6.5.1.7 A technical review and control system utilizing qualified reviewers shall function to perform the periodic or routine review of procedures and changes thereto. Details of this technical review process are provided in Section 6.5.3.

AUTHORITY 6.5.1.8 The Station Operations Review Committee shall:

{)Ml/cqf-,;;v

~ra.vid a. RseoH!Hlend to the General Manager - Salem Operation~{written approval rec..otr1111 en/a. f '""5 or disapproval of items considered under 6.5.1.6 (a) taYott~ (e) above.

~/;f_ !fs~ur4~""'

b. Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Vice President and Chief Nuclear Officer and the General Manager - Nuclear Safety Re~iew of disagreement between the SORG and the General Manager -

Salem Operations; however, the General Manager - Salem Operations shall have responsibility for resolution of such disagreements pursuant to 6.1.l above.

RECORDS f!MIJ ~EP4'RT$

6.5.1.9 The Station Operations Review Committee shall maintain written minutes of each meeting and copies shall be provided to the Vice President and Chief Nuclear Officer, the General Manager -tNuclear Safety &eview and the Manag~er Al {

-tOff Site Re<Tiew.

/' r- T:'1 TIQ L':' ~ /;f.-( 71,,,. ~'

n.,..t.(rtt11e f a.Ml' 1v (,(.&. et;. r ;,.~:re.'.!...)

6.5.2 NUCLEAR SAFETY REVIEW ..4:!'0 nv~JT FUNCTION 6.5.2.1 The Nuclear Safety Review Department ~shall function to provide the independent safety review program and audit of designated activities.

OSITION 6.5.2.2 hall consist of the General Manager - y Review, the:

Manager - On-Site afety Review Group (SRG), who is at least four' dedicated, full-time e *neers located on-site, and e Man~ger Off-Site Review Group (OSR) who is s orted by at leas our dedicated, full-time engineers located off-site.* The R sta s all possess experience and competence in the general areas lis Section 6.5.2.4. The General Manager and Managers shall determine w technical experts should assist in reviews of complex pr

Since Nuclear Department is located on Artificial Island "te, t erms "on-site" and "off-site" convey the distinction between inside and outside the station fence, respectively SALEM - UNIT 1 6- ~ I0 Amendment No.

ADMINISTRATIVE CONTROLS

_;:---r

__...------ I

NSR shall utili organizations to a system of qualified reviewers from other t§_~--------

Such qualified reviewers s NSR staff, and will not have 1 work.

its expertise in the disciplines ~ection 6.5.2.4.

meet the same qualif"

volved wi ion requirements as the performance of the original

.i

! The Manager - Off-Site Rev* and Staff shall meet exceed the i qualific'ations descr* in Section 4.7 of ANS 3.1(1981 d shall be guided by the provisio or independent review described in Section of ANSI Nl8.7 (19 (ANS 3.2). The Manager - On Site Review and staff will the qualifications described in Section 4.4 of ANS 3.1 (1981).

CONSULTANTS 6.5.2.3 Consultants shall be utilized as determined by the General Manager -

Nuslear ~afet:y Review t:e provide eHpert advice te the NSR. by f~e fl)"-~lear 5<\ Fef.'7

~i- fO" fhe <2.ichi(lf ti'2ce.~qr-y.

~~REVIEW 6RffiH' lo£*) tfjj)

~ ~ 6.5.2.4./ The Off-Site Review G~oup &SsR~shall function ~o provide independent

~~~~~ review and audit of designated activities in the areas of:

'(IJNCT(ON

a. Nuclear Power Plant Operations

b. Nuclear Engineering

c. Chemistry and Radiochemistry

d. Metallurgy

e. Instrumentation and Control

f. Radiological Safety

g. Mechanical Engineering

h. Electrical Engineering

i. Quality Assurance

j. Nondestructive Testing

k. Emergency Preparedness The OSR shall also function to eJeamine plant operating characteristics, NRG issuances, industry advisories, Licensee Event Reports, and other sources which may indicate areas for improving plant safety .

SALEM - UNIT 1 Amendment No.

COMPOSITION INSERT 1 TO SECTION 6.5.2 6.5.2.2 The Nuclear Safety Department, under the cognizance of the General Manager - Quality Assurance and Nuclear Safety, shall consist of the Manager - Nuclear Safety, the Offsite Safety Review staff (OSR) and the Onsite Safety Review Group (SRG) . The OSR staff and the SRG each consist of at least four dedicated, full-time engineers.

The Manager - Nuclear Safety and the Offsite Safety Review staff shall meet or exceed the qualifieations described in Section 4.7 of ANS 3.1 - 1981 and shall be guided by the provisions for independent review described in Section 4~3 of ANSI N18.7 - 1976 (ANS 3. 2) .

The Offsite Safety Review staff shall generally possess experience and competence in the areas listed in Section 6.5.2.4.1. A system of qualified reviewers from other technical organizations may be used to augment OSR staff expertise in the disciplines of Section 6.5.2.4.1, where appropriate. Such qualified reviewers shall meet the same qualification requirements as the Offsite Safety Review Staff, and shall not have been involved with performance of the original work.

The Onsite Safety Review Group staff shall meet or exceed the qualifications described in Section 4.4 of ANS 3.1 - 1981 .

ADMINISTRATIVE CONTROLS REVIEW ;;t &f?..ff..

6.5.2.4.t

-r/t .

The OS~l a~afety yEvaluations forj

~

review:

ichanges to procedures, equipment, or systemsjand 2:1' Jtests o~riments completed under the provisions of Section

-t50.59~to verify that such actions did not constitute an unreviewed safety question; ano-1/ -'- 1 re>TS or e,.."'°" . ..L 1 _r.metlf3

b. Proposed changes to procedures, equipment, or system,.. that involve an unreviewed safety question as defined in ~gctieR~

c. l'ro1rnsed tests or experiments that involve an unrevie~me. safety qugstion as defined in Seetion 50.59, lOGFR.

Proposed changes to Technical Specifications or to the Operating Licensei Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significancej et.. Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety;

All REPORTABLE EVENTS; All recognized indications of anl::::Ynanticipated deficiency in some aspect of design or operation of safety related structures, systems or componentsr +£""+- co,dtJ/ a.FFec. f nuc/f?'Q.r -s~fy ,,'

h,;:.. Reports and meeting minutes of the Station Operations Review Committee.

AUDITS 3

qf!/

5~Q~

6.5.2.4~ Audits of facility a c t i v i t i e s a r e re~uired te be performed under the cognizance ofa.esR fD listed bele'1.': Th~e t:i.ud,'fs sJ.Qtl e11c,.,.,pcu~:

@"os.-e ~.fQ_

a. The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.

b. The performance, training, and qualifications of the entire facility staff at least once per 12 months.

c. The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems, or method of operation that affect nuclear safety at least once per 6 months .

d.

SALEM - UNIT 1 The performance of activities required by the Operational Quality Assurance Program to meet the Criteria of Appendix t11'B~OCFR50, at least once per 24 months.

6-rn)~

0Y Amendment No.

ADMINISTRATIVE CONTROLS AUDITS (continued)

e.

f.

The Facility Emergency Plan and implementing procedures at least once per 12 months.

The Facility Security Plan and implementing procedures at least once per 12 months . /1 Qt).o./lfy liS<;tA.rat1ce &1.11(;1

/

g. Any other area of facility operation considered appropriate by the General Manager - Nuclear Safety Reoiew or the Vice President and Chief Nuclear Officer.

h. The Facility Fire Protection Program and implementing procedures at least once per 24 months.

T~e

i. i\;vlndependene fire protection and loss prevention program ;,.,.,pleme11fq,fio,,.,

inspsctign and audit shall ae performea at least once per 12 months utilizing eithe~ualified offsite or an outside fire protection ~~

An inspeetieH and audit of the fire prgtectigt:l and lgss pr*n sntion 1 program shall be performed by a qualified :utsi~,rfireLconsultant t least once per 36 months. (['nol~p.enolll~ Q_rofi'dio'i) <:.httl! lie uf;/i-eed.

The radiological environmental monitoring program and the results thereof at least once per 12 months.

,.,,~ V :riJ9e, r I The above audits ~ be conducted by the Nuelear Quality Assurance Department or an independent consult~~Fe~ttirea. Audit results and rscgrnsndations shall be reviewed by . ~IP o~R !ii-a-FF°")

~ TN$erfd..

~oNdSITE SAFETY REVIEW GROU:e_(sRG) 6.5.2.5,I The ondlite Safety Review Group (SRG) shall function to provide: the FUNC. r1orJ review of plant design and operating experience for potential opportunities to improve plant safety; the evaluation of plant operations and maintenance activities; and advice to management on the overall quality and safety of plant operations.

The SRG shall make recommendations for revised procedures, equipment modifications, or other means of improving plant safety to appropriate station/ corporate management.

RESPONSIBILITIES 9-6.5.2.5.A The SRG shall be responsible for:

a. Review of selected plant operating characteristics, NRG issuances, industry advisories, and other appropriate sources of plant design and operating experience information that may indicate areas for improving plant safety.

b. Review of selected facility features, equipment, and systems.

SALEM - UNIT 1 Amendment No.

INSERT 2 TO SECTION 6.5.2 RECORDS AND REPORTS 6.5.2.4.4 Records of OSR activities shall be maintained.

Reports of reviews and audits shall be prepared and distributed as indicated below:

a. The results of reviews performed pu.rsuant to Section 6.5.2.4.2 shall be reported to the Vice President and Chief Nuclear Officer at least monthly.

b. Audit reports prepared pursuant to Section 6.5.2.4.3 shall be forwarded by the auditing organization to the Vice President and Chief Nuclear Officer and to the "management positions responsible for the areas audited (1) within 30 days after completion of the audit for those audits conducted by the Quality Assurance Department, and (2) within 60 days after completion of the audit for those audits conducted by an independent consultant .

ADMINISTRATIVE CONTROLS RESPONSIBILITIES (continued)

c.

d.

Review of selected procedures and plant activities including maintenance, modification, operational problems, and operational analysis.

Surveillance of selected plant operations and maintenance activities to provide independent verification* that they are performed correctly and that human errors are reduced to as low as reasonably achievable.

"ttSR- AUTHORIT'£ /rl.t? Nu.G {ec..r s,..+ef( Oe.,,...r-1-m?fJ 6.5.2.6 ff8it~';{l report to and advise the Vice President and Chief Nuclear Officer on those areas of responsibility specified in Sections 6.5.2.4 and 6.5.2.5.

6.5.2.7 Records of NSR activities shall be prepared and maintained. Reports of reviews and audits shall be distributed as follows:

a. Reports of revieus encompassed by Section 6.5.2.4.1 above, shall be prepared, approved and forwarded to the Vice President and Chief Nuclear Offieer, within 14 days following completion of the review.

b. f.,udit reports encompassed by Section e.5.2. 11.2 above, shall be forwarded to the Vice President <!ffld Chief Nuclear Officer and to the management positions responsible for the areas audited with.in 30 da,s after eompletion of tho audit.

6.5.3 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.3.1 Programs required by Technical Specification 6.8 and other procedures which affect nuclear safety as determined by the General Manager - Salem Operations, other than editorial or typographical changes shall be reviewed as follows:

PROCEDURE RELATED DOCUMENTS 6.5.3.2 Procedures, Program and changes thereto shall be reviewed as follows:

a. Each newly created procedure, program or change thereto shall be independently reviewed by an individual knowledgeable in the subject area other than the individual who prepared the procedure, program or procedure change, but who may be from the same organization as the individual/group which prepared the procedure or procedure change. Procedures other than Station Administrative procedures will be approved by the appropriate Station Department Manager or by the hssistant General Manager - Salem Operations. Each Station Department Manager shall be responsible for a predesignated class of procedures. The General Manager - Salem Operations shall approve Station Administrative Procedures, Security Plan implementing procedures and Emergency Plan implementing procedures.

Not responsible for sign-off function SALEM - UNIT 1 Amendment No.

ADMINISTRATIVE CONTROLS PROCEDURE RELATED DOCUMENTS (continued)

b. On-the-spot changes to procedures which clearly do not change the intent of the approved procedures shall be approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator License. Revisions to procedures which may involve a change in intent of the approved procedures, shall be reviewed in accordance with Section 6.5.3.2.a above.

c. Individuals responsible for reviews performed in accordance with item 6.5.3.2a above shall be approved by the SORG Chairman and designated as Station Qualified Reviewers. A system of Station Qualified Reviewers, each of whom shall possess qualifications that meet or exceed the requirements of Section 4.4 of ANSI Nl8.l - 1971, shall be maintained by the SORG Chairman. Each review shall include a written determination of whether or not additional cross-disciplinary review is necessary. If deemed necessary, such review shall be performed by the appropriate designated review personnel.

rmines that the documents involved re31.(.1'l"e '4.. eE~;.a.;Hi---&+!2:R-3~~r:>H:t---&.38:-E~r--::HH!Yl:i-e-B, the documents shall be forwarded to<: l= R 50.5q for an independent review to S<<...fe+-t e-1Qfu.o.fi1>t-i determine whether or not an unreviewed safety question is involved, Pursuant to 10CFR50.59, NRG approval of items involving unreviewed safety questions or Technical Specification changes shall be obtained prior to implementation.

NON-PROCEDURE RELATED DOCUMENTS 6.5.3.3 Tests or experiments, changes to Technical Specifications, and to equipment or systems shall be forwarded for SORG review and also to an independent review to determine whether or not an unreviewed safety question is involved. The results of reviews will be provided to SORG.

Recommendations for approval are made by SORG to the General Manager - Salem Operations. Pursuant to 10CFR50.59, NRG approval of items involving unreviewed safety questions or requiring Technical Specification changes shall be obtained prior to implementation.

RECORDS A:tJf::> e_~Po~T5 6.5.3.4 Written records of reviews performed in accordance with it~6.5.3.2a above, including recommendations for approval or disapproval, shall be maintained. Copies shall be provided to the General Manager - Salem Operations, SORG, and/or NRG as necessary when their reviews are required.

f.l..e ~R ~+~

SALEM - UNIT 1 Amendment No.

ADMINISTRATIVE CONTROLS 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a. The Commission shall be notified and/or a report submitted pursuant to the requirements of Section 50.73 to 10CFR Part 50, and

b. Each REPORTABLE EVENT shall be reviewed by the SORG and the resultant Licensee Event Report submitted to and the Vice President and Chief Nuclear Officer.

6.7 SAFETY LIMIT VIOLATION 6.7.l The following actions shall be taken in the event a Safety Limit is violated:

a. The unit shall be placed in at least HOT STANDBY within one hour.

b. The NRG Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Vice President and Chief Nuclear Officer and General Manager -tNuclear Safety Review shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . @~ec/,*f.y fk~t<l*ll'P eui({)

c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the SORG. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to-prevent recurrence.

(il,,.Q 11'1-r 11-~~ (,( ta"c" Q.,,,,1

d. The Safety Limit Violation Report shall be submitted to the Commission, the General Manager - uclear Safety Review and the Vice President and Chief Nuclear Officer within 14 days of the violation .

SALEM - UNIT 1 6-m 16 Amendment No.

ADMINISTRATIVE CONTROLS 6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.

b. Refueling operations.

c. Surveillance and test activities of safety related equipment.

d. Security Plan implementation.

e. Emergency Plan implementation.

f. Fire Protection Program implementation.

g. PROCESS CONTROL PROGRAM implementation.

h. OFFSITE DOSE CALCULATION MANUAL implementation.

i. Quality Assurance Program for effluent and environmental monitoring.

6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed and approved in accordance with Specification 6.5.1.6 or 6.5.3, as appropriate, prior to implementation and reviewed periodically as set forth in administrative procedures.

6.8.3 On-the-spot changes to procedures of 6.8.1 above may be made provided:

a. The intent of the original procedure is not altered.

b. The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.

c. The change is documented and receives the same level of review and approval as the original procedure under Specification 6.5.3.2a within 14 days of implementation.

SALEM - UNIT 1 6-H- l9 11 Amendment No. ~

ADMINISTRATIVE CONTROLS 6.8.4 The following programs shall be maintained:

a. Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include (recirculation spray, safety injection, chemical and volume control, gas stripper, recombiners, ... ). The program shall include the following:

(i) Preventative maintenance and periodic visual inspection requirements, and (ii) Integrated leak test requirements for each system at refueling cycle intervals or less.

b. In-Plant Radiation Monitoring A program which will ensure the capability to accurately determine the airborne iodine concentration in areas under accident conditions. This program shall include the following:

(i) Training of personnel, (ii) Procedures for monitoring, and (iii) Provisions for maintenance of sampling and analyses equipment.

c. Secondary Water Chemistry A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation. This program shall include:

(i) Identification of a sampling schedule for the critical variables and the control points for these variables, (ii) Identification of the procedures used to measure the values of the critical variables, (iii) Identification of process sampling points, including monitoring at the discharge of the condensate pumps for evidence of condenser in-leakage.

(iv) Procedures for the recording and management of data, (v) Procedures defining corrective actions for off-control-point chemistry conditions, (vi) A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.

SALEM - UNIT 1 6-M./V, Amendment No. ~

ADMINISTRATIVE CONTROLS

d. Backup Method for Determining Subcooling Margin A program which will ensure the capability to accurately monitor the Reactor Coolant System Subcooling Margin. This program shall include the following:

(i) Training of personnel, and (ii) Procedures for monitoring

e. Postaccident Sampling A program* which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions. The program shall include the following:

(i) Training of personnel (ii) Procedures for sampling and analysis, (iii) Provisions for maintenance of sampling and analysis equipment.

It is acceptable if the licensee maintains details of the program in plant operation manuals.

SALEM - UNIT 1 Amendment No. 67

ADMINISTRATIVE CONTROLS 6.9 REPORTING REQUIREMENTS ROUTINE REPORTS AND REPORTABLE OGGURRENGES 6.9.1 In addition to the applicable reporting requirements of Title 10, Code

/.:~of Federal Regulations, the following reports shall be submitted to the

~~Adrninistrator~Offiee of Inspeetion and Enforeement unless otherwise noted. ~

STARTUP REPORT 6.9.L.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

ANNUAL REPORTt if 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year c2__

following initial critieality.e

~ri __.,,,.t'-----

~47 A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.

SALEM - UNIT 1 Amendment No 67

ADMINISTRATIVE CONTROLS

6.9.1.5 Reports required on an annual basis shall include:

a. A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their as~gx,iated man rem exposure according to work and job functionsf t}-e.g., reactor operations and surveillance, inservice inspection~ routine maintenance, special maintenance (describe maintenance), waste processing, and refueling.

The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

b. The complete results of steam generator tube inservice inspections performed during the report period (reference Specification 4 4 5 5

* * *b0 ~SEE ~11ser+-1r MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission, Docume t n rol Desk, Washington, D.C. 20555 with a copy to the Regio11al~

Administrato~ * * , no later than the 15th of each month following the calendar month covered by the report.

6. 9 .1. 7 Tne REPORTABLE OCCURRENCES of Speci fi cati oris 6. 9 .1. 8 a11d 6. 9 .1. 9 below, ir:ich1ding corrective actions ai:1d meas'lres to prevent recurrence, shall be PepePted to tRe NRG. SupplemeRtal reports may be required to f~lly describe fiRal Peselutier:i of eccurreRce. IR case ef cerrected er supplemeRtal repor-t-~,

,a licensee event report shall be completed and reference shall be made to the original report date PROMPT NOTIFICATION WITll WRITTEN FOLLOWUP 6.9.1.8 The types ef eveRts listed belew shall be reported witniR 24 heurs by telephor:ie and confirmed by telegrapR, mailgram, er facsimile traRsmissioR te tRe AdmiRistrator of tRe RegioRal Office, or Ris desigRate Re lateP thaR the first werkiRg day follewiRg tRe ever:it, witR a writteR followup report witRiR 14 days. TRe writter:i followup report sRall iRclude, as a miRim~m, a completed

-cepy of a lieeRsee eveRt report form. IRformatioR provided OR tRe liceRsee eveRt report form sRall be supplemeRted, as Reeded, by additieRal RafPative

-material to provide complete explaRatioR of the circ~mstaRces s~rrouRdiRg the eveRt.

¥12:1- This tabulation supplements the requirements of section 20.407 of 10 CFR Part 20 .

SALEM - UNIT 1 Amendment No.~

INSERT TO SECTION 6.9.1.5

c. The results of any specific activity analyses in which the primary coolant exceeded the limits of Specification 3.4.8. The following information shall be included: (1) Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while the limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than the limit. Each result should include date and time of sampling and the radioiodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of -the specific activity above the steady state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit

ADMINISTRATIVE CONTROLS

a. Failure of the reactor protection system or other systems subject t limiting safety system settings to initiate the required protectiv function by the time a monitored parameter reaches the setpoint specified as the limiting safety system setting in the technic specifications or failure to complete the required protective function.

Operation of the unit or affected systems when any operation subject to a limiting condition for operatio conservative than the least conservative aspect of th limiting condition for operation established in* the technica specifications.

c. Ab ormal degradation discovered in fuel cladding pre ure boundary, or primary containment.

d. Reactiv"ty anomalies involving disagreement ith the predicted value of react ity balance under steady state c ditions during power operation eater than or equal to 1% de a k/k; a calculated reactivity 6 lance indicating a SHUTDO MARGIN less conservative than specifie in the technical speci cations; short-term reactivity incr ases that correspon to a reactor period of less than 5 seconds o if subcritical, an unplanned reactivity insertion of more than 0.5% elta k/k; currence of any unplanned criticality.

e. Failure or malfunction or more components which prevents or could prevent, by itself, e fulfillment of the functional requirements of system(s ed to cope with accidents analyzed in the SAR.

f. Personnel error or ocedural i adequacy which prevents or could prevent, by itself., the fulfillme t of the functional requirements of systems requi ed to cope with a idents analyzed in the SAR.

g. Conditions ar, sing from natural or ma made events that, as a direct result of t e event require unit shutdo ; operation of safety systems, other protective measures re ired by technical specific tions.

h. Erro~ discovered in the transient or acciden analyses or in the met ods used for such analyses as described in e safety analysis r ort or in the bases for the technical specifi tions that have or ould have permitted reactor ope~ation in a manner ess conservative than assumed in* the analyses.

Performance of structures, systems,\or components that equires remedial. ~ction or corrective measures to prevent operat1 n in a manner less conservative than assumed in the accident anal es in the safety analysis report or technical specifications bases or discovery during unit life of conditions not specifically con "dered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition.

ADMINISTRATIVE CONTROLS

j. Offsite releases of radioactive materials in liquid and gaseous effluents that exceed the limits of Specification 3.11.1.1 or 3.11.2.1.

Exceeding the limits in Specification 3.11.1.4 or 3.11.2.6 for storage of radioactive materials in the listed tanks. The writ follow-up report shall include a schedule and a description a ctivities planned and/or taken to reduce the contents to w* hin the cified limits.

- *~-**/

6. 9 .1. 9 The type of events 1 i sted be 1ow sha 11 he reports to the U.S. Nuclear Regulatory Commission, Document C ntrol Desk, Washington, D.C. 20 5, with a copy to the Regional Administ ator of the Regional Office withi thirty days of occurrence of the ev t. The written report shall include, a a minimum, a completed copy of a icensee event report form. Information rovided on th* licensee event eport form shall be supplemented, as needed, additional narrative mater* 1 to prov.ide complete explanation of th~ circumst nces surrounding ~he even ,

a. Reactor protection stem or engineered afety feature instrument settings which are fo nd to be less con ervative than those established by the tee ical specific ions but which do not prevent the fulfillment of the nctional re uirements of affected systems.

b. Conditions leading .permitted by a limiting condition required by a limiting condition

c. Observed inadequacies in the imp ementation of administrative or procedural controls which reate to cause reduction of degree of redundancy provided in re ctor prot ction systems or engineered safety feature systems.

d. Abnormal degradation systems other t an those specified in 6.9.1.8.c above desi ned to resulting from the fission pr, cess.

e. of 1) more than 1 curie of radioactive material in li id effluents, 2) more than 150 curies of noble gas in gaseous ef uents. The report of an unplanne offsite release of radioactive aterial shall include the following 'nformation.

1. A the event and equipment

2. unplanned release.

prevent recurrence.

Consequences of the unplanned release.

6-18 Amendment No.

ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT*

Cf)~ Routine Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.

The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental survefllance activities for the report period, including a comparison with preoperational studies with operational controls (as appropriate), and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.

The reports shall also include the results of land use censuses required by Specification 3.12.2. The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all measurements taken during the period pursuant to the Table and Figures in the environmental radiation section of the ODCM; as well as summarized and tabulated results of locations specified in these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.

The missing data shall be submitted as soon as possible in a su lementar report. one coterlf)~ 9:unp tll~ <>c.:t 1oflS nea.r +l.e Si:-/£ soaf/J()l/(2.'( Ql)c{ Q. Si?C<N')O!

c1>ver,"fl tlw "770re of<siu.rd- /c>ceifi'o/IS/ Q.{(

The reports shall also include the following: a summary description of the radiological environmental monitoring program; at least two legible map~~

.. _ *

keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program, required by Specification 3.12.1; and discussion of all analyses in which the LLD required by Table 4.12-1 was not achievable.

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT*

~-I- Routine Radioactive Effluent Release Reports covering the operation of the unit during the previous six mont,hs of operation shal 1 be submitted within 60 days after January 1 and July 1 of each year.

The Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21. "Measuring, Evaluating, and

A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

SALEM - UNIT 1 Amendment No. ~

ADMINISTRATIVE CONTROLS Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Pl a~, 11 Revision 1, June 1974, with data summarized on a quarterly basis following the format* of Appendix B thereof. s The Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured),

or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability~~This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 5.1-3) during the report period.

All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL.

The Radioactive Effluent Release Report to be submitted 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose

contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.

The Radioactive Effluent Release Reports shall include the following information for each class of solid waste (as defined by 10 gj'FPart 61) shipped offsite during the report period:

a. Container volume,

b. Total curie quantity (specify whether determined by measurement or c.

estimate),

Principal radionuclides (specify whether determined by measurement or estimate),

f

d. Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),

tJ° In lieu of submission with the first half year Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

SALEM - UNIT 1 Amendment No. @

~~-

ADMINISTRATIVE CONTROLS

e. Type of container (e.g., LSA, Type A, Type B, Large Quantity), and

f. So~idification agent or absorbent (e.g., cement, urea formal~yde).

The Radioactive Effluent Release Reports shall include a list of descripti~

of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.

_ The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and*to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification 3.12.2. .

~SEE .:r:AJSERI *'

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory

~~' Document Control Desk, Washington, D.C. 20555 with a copy to the

~ ~~Administrato;~io~aJ Qffiee within the time period specified for each report. f2.~ ,-o. 11 I * .

- I 6.10 RECORD RETENTION In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be re;j_ned for at least the minimum period indicated. A:l..~

6.10.1 The following records shall be retained for at least five years:

a. Records and logs of unit operation covering time interval at each power level.

b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

r-----_.

c. ~ IDORTABLE ecetJBflFNefS1 submitted to the Commission.

d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

@. Rece~as ~t Peaetef tests a"d expef1me"t~

@?(. Records of changes made to Operating Procedures required by Specification 6.8.1. *

~ Records of radioactive shipments.

~- Records of sealed source and fission detector leak tests and results.

'. Records of annual physical inventory of al1 sealed source material of record.

SALEM - UNIT 1 Amendment No. ~

INSERT TO SECTION 6.9.1 RADIAL PEAKING FACTOR LIMIT REPORT RTP 6.9.l.9 The F limits for Rated Thermal Power (F ) for all xy xy core planes containing bank "D" control rods and all unrodded core planes and the plot of predicted heat flux hot channel factor times relative power (F~*PREL) vs. Axial Core Height with the limit envelope shall be provided to the NRG Document Control Desk with copies to the Regional Administrator and the Resident Inspector. The Report shall be provided to the Commission no later than thirty days subsequent to initial use of F limits for xy surveillance unless otherwise approved by the Commission by letter.

In addition, in the event that the limit should change, requiring a new submittal or an amended submittal to the Peaking Factor Limit Report, it will be submitted within thirty days of the date the limit would become effective unless otherwise approved by the Commission by letter .

. f ormation Any in . nee d e d to support FRTP wi* 11 b e b y request f ram t h e NR C an d need not be included in this report.

xy

ADMINISTRATIVE CONTROLS 6 .10. 2 The following records shall be retained** for the duration of the Unit Operating License:

a. Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Rep!Jrt.

b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

c. Records of radiation exposure for all individuals entering*

radiation control areas.

d. Records of gaseous and liquid radioactive material released to the environs.

e. Records of transient or operational cycles for those facility components identified in Table 5.7-1.

f. Records of reactor tests and experiments.

g. Records of training and qualification for current members of the plant staff.

h. Records of in-service inspections performed pursuant to these Technical Specifications.

i. Records of Quality Assurance activities required by the QA Manual.

j.

k.

Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

Records of a.cf?v;fN'S o+ ose_ a.nof ,nee/.:~> .,-F ;-fs preofece>GO".J rl..e Nuc./ea.r i2e1Nec.J Boe>rd, and~RB"";--~~~-.:...:::.::..:..:.=-=-::~~

1. Records for Environmental Qualification which are covered under the provisions of Paragraph 6.16.

m. Records of the service lives of all hydraulic and mechanical snubbers including the date at which the service life commences and associated installation and maintenance records.

n. Records of secondary water sampling and water quality.

o. Records of analyses required by the radiological environmental monitoring program which would permit evaluation of the accuracy of the analysis at a later date. This should include procedures effective at specified times and QA records showing that these procedures were followed.

SALEM - UNIT 1 Amendment No.U--

ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATlON AREA 6.12.1 In lieu of the "control device" or "alarm signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20, each high radiation area in which the in~nsity of radiation is greater than 100 mremjhr but less than 1000 mremjh~shall be barricaded and conspicuously posted as a High Radiation Area

~and entrance thereto shall be controlled by issuance of a Radiation Exposure

\.:../ ~- Any individual or group of individuals permitted to enter such areas shal e provided with or accompanied by one or more of the following:

-~-F-M.---e'h-;d'h-ro.of---:-;*a_f_'"Yl-J A radiation monitoring device which continuously indicates the a re.::t 15 es fakll>h el a*

radiation dose rate in the area .

..f;r tl ~ ri"oof e -F 3 0 .

~y~ or /e~s, J;red b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated survei//o.11ce fo pre- dose is received. Entry into such areas with this monitoring device vell f u. M u+J.o,;"l:e) ~ay be made after the dose rate _level in the area has been en fr( .rio.y lJe u~eJ established and personnel have been made knowledgeable of them.

rnsfeCA.J o-F +he c. A health physics qualified individual (i.e., qualified in radiation a.cc..e£S cot1f-ra 15 protection procedures) with a radiation dose rate monitoring device d eof ~ berte.J who is responsible for providing positive control over the FR.. ~6. ';lo3 activities within the area and shall perform periodic radiation surveillance at the frequency specified by the ~aeilitry llcBlth Cc 'J)(iii)(Lj), ~sl!eist in di.e Radiation Work Permit.

6.12.2 In addition to th~equirements of 6.12.1, areas accessible to personnel with radiation level~such that' a major portion of the body could receive in one hour a dose greater than 1000 mrem shall be provided with locked doors to prevent unauthorized entr and the keys shall be maintained under the administrative control of the Senio Shift Supervisor on duty and/or

senior Supervisor - Radiation Protection. Doors shall remain locked except during periods of access by personnel under an approved Radiation Work Permit which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area. For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour or personnel escorted by personnel shall be exemp~ from the RWP issuance requirement ng the performance of their assigned radiation protection duties, provided hey are otherwise following plant radiation protection procedures for entry into high radiation areas.

Tti,5 /s norw1.ffy o/e..f:,'ned q,s +/.e /eve.( q_+ J;s-feu1ce o-F 18 Inc.hr;?<; Fio"1 a.

-the sal{rce or a.c.c..e~s;b/e s-ur~ce.

SALEM - UNIT 1 Amendment No. ~*

ADMINISTRATIVE CONTROLS a dose in excess of 1000 mrem~hat are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonable constructed around the individual areas, then that area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device. In lieu of the stay time specification of the RWP, direct or remote (such as use of closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.

6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.

6.13.2 Licensee initiated changes to the PCP:

1. Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change(s) was made. This submittal shall contain:

a. Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information;

b. A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and

c. Documentation of the fact that the change has been reviewed and found acceptable by the SORG.

2. Shall become effective upon review and acceptance by the SORG.

6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.

6.14.2 Licensee initiated changes to the ODCM:

1. Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change(s) was made. This submittal shall contain:

a. Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information. Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change(s);

~ Measttrement: ma:de at 18" from source of radioaetivit:y.

SALEM - UNIT 1 Amendment No. ~

ADMINISTRATIVE CONTROLS

b. A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determination; and

c. Documentation of the fact that the change has been reviewed and found acceptable by the SORC.

2. Shall become effective upon review and acceptance by the SORC.

6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 6.15.1 Licensee initiated major changes to the radioactive waste system (liquid, gaseous and solid):

1. Shall be reported to the Commission in th~AR for the period in which the evaluation was reviewed by (SORC). The discussion of each change~ sha 11 contain: 4.f fie e-"411 ~

a. A summary of the evaluation that led to the determination could be made in accordance with lO'cFR" :p:a:p:t '"50. 59;

b. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; *

c. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems;

d. An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto;

e. An evaluation of the change, which shows the expected maximum exposures to individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto;

f. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releas~s for the period prior to when the changes are to be made;

g. An estimate of the exposure to plant operating personnel as a result of the change; and

h. Documentation of the fact that the change was reviewed and found acceptable by the (SORC).

2. Shall become effective upon review and acceptance by the SORC ..

SALEM - UNIT 1 Amendment No.<@"'

ADMINISTRATIVE CONTROLS 6.16 ENVIRONMENTAL QUALIFICATION 6.16.1 By FIS la.teP tl:laR Jur:ie ~Q, 1982/all safety-related electrical equipment in the facility shall be qualified in accordance with the provisions of:

Division of Operating Reactors "Guidelines for Evaluating Environmental Qualification of Class lE Electrical Equipment in Operating Reactors" (DOR Guidelines); or, NUREG-0588 "Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment, 11 December 1979. Copies of these 'documents are attached to Order for Modification of Li cen,ee No.

DPR-70 dated October 24, 1980. 5

. ~ ~hq)/

6 .16. 2 8-y FIS later than December 1, 1~ /comp 1ete and aud i tab 1e records fflt:ts-t

be available and maintatned at a central location which describe the environmental qualification method used for all safety-related electrical equipment in sufficient detail to document the degree of compliance with the DOR Guidelines or NUREG-0588. The1eafter, /Such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified.

SALEM - UNIT 1 Amendment No. 59 I

J

UNIT 1 RETYPED PAGES DEFINITIONS SECTION 1.0 DEFINITIONS DEFINED TERMS. 1-1 ACTION . . . . . . . . 1-1 AXIAL FLUX DIFFERENCE 1-1 CHANNEL CALIBRATION 1-1 CHANNEL CHECK 1-1 CHANNEL FUNCTIONAL TEST 1-1 CONTAINMENT INTEGRITY 1-2 CONTROLLED LEAKAGE . . 1-2 CORE ALTERATION 1-2 QOSE EQUIVALENT I-131 1-2 E-AVERAGE DISINTEGRATION ENERGY 1-3 ENGINEERED SAFETY FEATURE RESPONSE TIME 1-3 FREQUENCY NOTATION . . . . . . . . 1-3 GASEOUS RADWASTE TREATMENT SYSTEM. 1-3 IDENTIFIED LEAKAGE . . . . . . . . 1-3 MEMBER(S) OF THE PUBLIC . . . . 1-4 OFFSITE DOSE CALCULATION MANUAL (ODCM) 1-4 OPERABLE - OPERABILITY 1-4 OPERATIONAL MODE . . . . . 1-4 PHYSICS TESTS 1-5 PRESSURE BOUNDARY LEAKAGE 1-5 PROCESS CONTROL PROGRAM (PCP) 1-5 PURGE-PURGING . . . . . . 1-5 QUADRANT POWER TILT RATIO 1-5 RATED THERMAL POWER 1-5 REACTOR TRIP SYSTEM RESPONSE TIME 1-6 REPORTABLE EVENT 1-6 SHUTDOWN MARGIN 1-6 SITE BOUNDARY 1-6 SOLIDIFICATION . 1-6 SOURCE CHECK 1-6 STAGGERED TEST BASIS 1-6 THERMAL BOWER 1-7 UNIDENTIFIED LEAKAGE 1-7 UNRESTRICTED AREA 1-7 VENTILATION EXHAUST TREATMENT SYSTEM 1-7 VENTING 1-7 SALEM - UNIT 1 I Amendment No.

ADMINISTRATIVE CONTROLS

SECTION 6.1 6.2 RESPONSIBILITY ORGANIZATION 6-1 Onsite and Offsite Organizations 6-1 Facility Staff . . 6-1 Shift Technical Advisor 6-7 6.3 FACILITY STAFF QUALIFICATIONS 6-7 6.4 TRAINING . . . . . . . . . . . . . . . . . . . . . . 6-7 6.5 REVIEW AND AUDIT 6.5.1 STATION OPERATIONS REVIEW COMMITTEE Function 6-8 Composition 6-8 Alternates 6-8 Meeting Frequency 6-8 Quorum . . . . . 6-8 Responsibilities 6-9 SORG Review Process 6-10 Authority . . . . . 6-10 Records and Reports 6-10 6.5.2 NUCLEAR SAFETY REVIEW Function 6-10 Composition 6-10 Consultants 6-11 Off-Site Review (OSR) 6-11 Function 6-11 Review 6-12 Audits 6-12 Records and Reports 6-13 On-Site Safety Review Group (SRG) 6-13 Function . . . . 6-13 Responsibilities 6-14 Authority . . . . 6-14 SALEM - UNIT 1 XVIII Amendment No.

ADMINISTRATIVE CONTROLS INDEX SECTION PAGE 6.5.3 TECHNICAL REVIEW AND CONTROL 6-15 6.6 REPORTABLE EVENT ACTION 6-15 6.7 SAFETY LIMIT VIOLATION 6-16 6.8 PROCEDURES AND PROGRAMS 6-16 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS 6-19 6.9.2 SPECIAL REPORTS 6-23 6.10 RECORD RETENTION 6-23 6.11 RADIATION PROTECTION PROGRAM 6-25

6.12 HIGH RADIATION AREA .

6.13 PROCESS CONTROL PROGRAM 6.14 OFFS I TE DOSE CALCULATION MANUAL 6-25 6-26 6-27 6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 6-27 6.16 ENVIRONMENTAL QUALIFICATION 6-29

SALEM - UNIT 1 XIX Amendment No.

DEFINITIONS REACTOR TRIP SYSTEM RESPONSE TIME 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until loss of stationary gripper coil voltage.

REPORTABLE EVENT 1.27 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10CFR Part 50.

SHUTDOWN MARGIN 1.28 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all full length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn.

SITE BOUNDARY 1.29 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee, as shown in Figure 5.1-3, and which defines the exclusion area as shown in Figure 5.1-1.

SOLIDIFICATION 1.30 SOLIDIFICATION shall be the conversion of wet radioactive wastes into a form that meets shipping and burial ground requirements.

SOURCE CHECK 1.31 SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

STAGGERED TEST BASIS 1.32 A STAGGERED TEST BASIS shall consist of:

a. A test schedule for (n) systems, subsystems, trains, or other designated components obtained by dividing the specified test interval into (n) equal subintervals,

SALEM - UNIT 1 1-6 Amendment No.

INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

LIMITING CONDITION FOR OPERATION 3.3.3.8 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm/ trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY: At all times.

ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable or change the setpoint so it is acceptably conservative.

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12. Exert best efforts to return the instrument to operable status within 30 days and, if unsuccessful, explain in the next semi-annual radioactive effluent release report why the inoperability was not corrected in a timely manner .

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.8 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-12 .

SALEM - UNIT 1 3/4 3-58 Amendment No.

INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive gaseous effluent Monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm/ trip setpoints set to ensure that the limits of Specification 3.11.2.l are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with the ODCM.

APPLICABILITY: As shown in Table 3.3-13 ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable or change the setpoint so it is acceptably conservative.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13. Exert best efforts to return the instrument to operable status within 30 days and, if unsuccessful, explain in the next semi-annual radioactive effluent release report why the inoperability was not corrected in a timely manner.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, AND CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-13 .

SALEM - UNIT 1 3/4 3-64 Amendment No.

REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY

LIMITING CONDITION FOR OPERATION 3.4.8 a.

The specific activity of the primary coolant shall be limited to:

< 1.0 Ci/gram DOSE EQUIVALENT I-131, and

b. < 100/E Ci/gram.

APPLICABILITY: MODES 1, 2, 3, 4 and 5 ACTION:

MODES 1, 2 and 3*

a. With the specific activity of the primary coolant > 1.0 Ci/gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval or exceeding the limit line shown on Figure 3.4-1, be in at least HOT STANDBY with T avg

< 500°F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With the specific activity of the primary coolant> 100/E Ci/gram, be in at least HOT STANDBY with T < 500°F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

avg MODES 1, 2, 3, 4 and 5

a. With the specific activity of the primary coolant > 1.0 Ci/gram DOSE EQUIVALENT I-131 or > 100/E Ci/gram, perform the sampling and analysis requirements of item 4a of Table 4.4-2 until the specific activity of the primary coolant is restored to within its limits.

SURVEILLANCE REQUIREMENTS 4.4.8 The specific activity of the primary coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-4 .

*With T avg SALEM - UNIT 1 "7 500°F.

3/4 4-20 Amendment No.

INTENTIONALLY LEFT BLANK SALEM - UNIT 1 3/4 4-21 Amendment No.

RADIOACTIVE EFFLUENTS LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, and

b. During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits .

b. The provisions of Sp.ecification 3. 0. 3 and 3. 0. 4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents shall be determined in accordance with the ODCM at least once per 31 days.

SALEM - UNIT 1 3/4 11-5 Amendment No.

RADIOACTIVE EFFLUENTS LIQUID RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.1.3 The liquid radwaste treatment system shall be used to reduce the radioactive materials liquid wastes prior to their discharge when the projected cumulative doses due to the liquid effluent from each reactor to UNRESTRICTED AREAS (see Figure 5.1-3) exceed 0.375 mrem to the total body or 1.25 mrem to any organ during any calendar quarter.

APPLICABILITY: At all times.

ACTION:

a. With the radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that includes the following information:

1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability.

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action(s) taken to prevent a recurrence.

b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.3 Doses due to liquid releases shall be projected at least once per 31 days in accordance with the ODCM.

SALEM - UNIT 1 3/4 11-6 Amendment No.

RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES

LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site areas and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and,

b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILITY: At all times ACTION:

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the release and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with the ODCM at least once per 31 days.

SALEM - UNIT 1 3/4 11-12 Amendment No.

RADIOACTIVE EFFLUENTS DOSE - IODINE-131. TRITIUM. AND RADIONUCLIDES IN PARTICULATE FORM

LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from iodine-131, from tritium, and from all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ and,

b. During any calendar year: Less than or equal to 15 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated air dose from the release of iodine-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the release and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the ODCM at least once per 31 days .

SALEM - UNIT 1 3/4 11-13 Amendment No.

RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases, from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3), exceed 0.625 mrad for gamma radiation and 1.25 mrad for beta radiation in any calendar quarter. The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases, from each reactor unit, from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) would exceed 1.875 mrem to any organ in any calendar quarter.

APPLICABILITY: At all times.

ACTION:

a. With gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that includes the following information:

1. Explanation of why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action(s) taken to prevent a recurrence.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.4 Doses due to gaseous releases from the site shall be projected at least once per 31 days in accordance with the ODCM .

SALEM - UNIT 1 3/4 11-14 Amendment No.

SOLID RADIOACTIVE WASTE LIMITING CONDITION FOR OPERATION

3.11.3. The solid radwaste system shall be used in accordance with a PROCESS CONTROL PROGRAM to process wet radioactive waste to meet shipping and burial ground requirements.

APPLICABILITY: At all times.

ACTION:

a. With the provisions of the PROCESS CONTROL PROGRAM not satisfied, suspend shipments of defectively processed or defectively packaged solid radioactive wastes from the site.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.3. The PROCESS CONTROL PROGRAM shall be used to verify the SOLIDIFICATION of at least one representative test specimen from at least every tenth batch of each type of wet radioactive waste (e.g., filter sludges, spent resins, evaporator bottoms, boric acid solutions, and sodium sulfate solutions).

a. If any test specimen fails to verify SOLIDIFICATION, the SOLIDIFICATION of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative SOLIDIFICATION parameters can be determined in accordance with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION. SOLIDIFICATION of the batch may then be resumed using the alternative SOLIDIFICATION parameters determined by the PROCESS CONTROL PROGRAM.

b. If the initial test specimen from a batch of waste fails to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall provide for the collection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least three consecutive initial test specimens demonstrate SOLIDIFICATION. The PROCESS CONTROL PROGRAM shall be modified as required, as provided in Specification 6.13, to assure SOLIDIFICATION of subsequent batches of waste .

SALEM - UNIT 1 3/4 11-17 Amendment No.

RADIOACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE LIMITING CONDITION FOR OPERATION 3.11.4. The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrems).

APPLICABILITY: At all times ACTION:

a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specification 3.ll.l.2a, 3.ll.l.2b, 3.ll.2.2a, 3.ll.2.2b, 3.ll.2.3a, or 3.ll.2.3b, calculations should be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the limits of this Specification have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report.

It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action an the request is complete .

SALEM - UNIT 1 3/4 11-18 Amendment No.

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1. The radiological environmental monitoring program shall be conducted as specified in Table 3.12-1.

APPLICABILITY: At all times.

ACTION:

a. With the radiological environmental monitoring program not being conducted as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Specification 6.9.1.7, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2, and 3.11.2.3. When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1) concentration (2)

+ + ... 1.0 reporting level (1) reporting level (2)

When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a member of the public is equal to or greater SALEM - UNIT 1 3/4 12-1 Amendment No.

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM

LIMITING CONDITION FOR OPERATION ACTION: (Cont'd) than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2, and 3.11.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.12-1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days. The specific locations from which samples were unavailable may then be deleted from the monitoring program.

Pursuant to Specification 6.9.1.8, identify the cause of the unavailability of samples and the new location(s) for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report. Include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

d. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the locations specified in the ODCM and shall be analyzed pursuant to the requirements of Table 4.12-1.

SALEM - UNIT 1 3/4 12-2 Amendment No.

TABLE 3.12-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Water Airborne Particul~te Fish Milk Food Products Analysis (I!CiL'.1} or Gases (I!CiL'.m ) (I!Ci!Kg, wet) (I!CiL'.12 (I!Ci/Kg, wet) 4 H-3 2 x 10 (*)

3 4 Mn-54 1 x 10 3 x 10 2 4 Fe-59 4 x 10 1 x 10 3 4 Co-58 1 x 10 3 x 10 Co-60 2 4 3 x 10 1 x 10 2 4 Zn-65 3 x 10 2 x 10 2

Zr-Nb-95 4 x 10 2

I-131 2 0.9 3 1 x 10 3 3 Cs-134 30 10 1 x 10 60 1 x 10 3 3 Cs-137 so 20 2 x 10 70 2 x 10 2 2 Ba-La-140 2 x 10 3 x 10

(*) For drinking wate4 samples. This is a 40CFR141 value. If no drinking water pathway exists, a value of 3 x 10 pCi/l may be used.

SALEM - UNIT 1 3/4 12-8 Amendment No.

TABLE 4.12-1 MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION (LLD)a,b Water Airborne Particul~te Fish Milk Food Products Sediment Analysis (2Ci.:'.'.l) or Gases (2Ci.:'.'.m ) (2Ci.:'.'.Kg, wet) (2Ci.:'.'.l) (11Ci.:'.'.Kg, wet) (11Ci.:'.'.Kg, dry) gross beta 4 1 x 10- 2 H-3 2000c Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-Nb-95 15 ld 2 I-131 7 x 10- 1 60 2

Cs-134 15 5 x 10- 130 15 60 150 2

Cs-137 18 6 x 10- 150 18 80 180 Ba-La-140 15 15 SALEM - UNIT 1 3/4 12-9 Amendment No.

TABLE 4.12-1 (Cont'd)

TABLE NOTATION a

Required detection capabilities for thermolurninescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13, Rev. 1, July, 1977.

b The LLD is defined in Table 4.11-1.

c If no drinking water pathway exists, a value of 3000 pCi/l may be used.

d LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.

SALEM - UNIT 1 3/4 12-10 Amendment No.

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS

LIMITING CONDITION FOR OPERATION 3.12.2. A land use census shall be conducted and shall identify within a distance of 8 km (S miles) the location in each of the 16 meteorological sectors of the nearest milk 2nimal, t2e nearest residence and the nearest garden* of greater than SO m (SOO ft ) producing broad leaf vegetation. (For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify within a distance of S km (3 miles) the locations in each of the 16 ~eteorological sectors of all milk animals and all gardens of greater than SO m producing broad leaf vegetation.

APPLICABILITY: At all times.

ACTION:

a. With a land use census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, identify the new location(s) in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.8.

b. With a land use census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, add the new location(s) to the radiological environmental monitoring program within 30 days. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s) (via the same exposure pathway) may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted. Pursuant to Specification 6.9.1.8, identify the new location(s) in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7.

Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Q in lieu of the garden census.

Specifications for broadleaf vegetation sampling in Table 3.12-l.4c shall be followed, including analysis of control samples.

SALEM - UNIT 1 3/4 12-11 Amendment No.

INTENTIONALLY LEFT BLANK

SALEM - UNIT 1 3/4 12-12 Amendment No.

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3. INTERLABORATORY COMPARISON PROGRAM

LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission.

APPLICABILITY: At all times.

ACTION:

a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Envirorunental Operating Report pursuant to Specification 6.9.1.7.

b. The provisions of Specifications 3.0.3 and 3.0.4. are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.3 A summary of the results obtained as part of the above required Interlaboratory Comparison Program and in accordance with the ODCM shall be included in the Annual Radiological Envirorunental Operating Report pursuant to Specification 6.9.1.7.

SALEM - UNIT 1 3/4 12-13 Amendment No.

REACTOR COOLANT SYSTEM BASES 3/4.4.8 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the resulting 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months doses at the site boundary will not exceed an appropriately small fraction of Part 100 limits following a steam generator tube rupture accident in conjunction with an assumed steady state primary-to-secondary steam generator leakage rate of 1.0 GPM. The values for the limits on specific activity represent interim limits based upon a parametric evaluation by the NRG of typical site locations. These values are conservative in that specific site parameters of the Salem site, such as site boundary location and meteorological conditions, were not considered in this evaluation. The NRG is finalizing site specific criteria which will be used as the basis for the reevaluation of the specific activity limits of this site.

This reevaluation may result in higher limits.

Reducing T to <500°F prevents the release of activity should a steam generator tube ~~~ture since the saturation pressure of the primary coolant is below the lift pressure of the atmospheric steam relief valves. The surveillance requirements provide adequate assurance that excessive specific activity levels in the primary coolant will be detected in sufficient time to take corrective action. Information obtained on iodine spiking will be used to assess the parameters associated with spiking phenomena. A reduction in frequency of isotopic analyses following power changes may be permissible if justified by the data obtained .

SALEM - UNIT 1 B 3/4 4-5 Amendment No.

6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.l The General Manager - Salem Operations shall be responsible for overall facility operation and shall delegate, in writing, the succession to this responsibility during his absence.

6.1.2 The Senior Nuclear Shift Supervisor, or during his absence from the control room a designated individual, shall be responsible for the control room command function. A management directive to this effect, signed by the Vice President and Chief Nuclear Officer, shall be reissued to all station personnel on an annual basis.

6.2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include positions for activities affecting the safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shall be established and defined from the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and.updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the Salem Updated Final Safety Analysis Report and updated in accordance with 10 CFR 50.7l(e).

b. The General Manager - Salem Operations shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

c. The Vice President and Chief Nuclear Officer shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

d. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

6.2.2 FACILITY STAFF The facility organization shall be subject to the following:

a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1; SALEM - UNIT 1 6-1 Amendment No.

ADMINISTRATIVE CONTROLS FACILITY STAFF (continued)

b.

c.

At least one licensed Reactor Operator shall be in the control room when fuel is in the reactor. In addition, at least one licensed Senior Reactor Operator shall be in the control room area at all times.

All CORE ALTERATIONS shall be observed and directly supervised by a licensed Senior Reactor Operator who has no other concurrent responsibilities during this operation.

d. A site Fire Brigade of at least 5 members shall be maintained onsite at all times*. The Fire Brigade shall not include 4 members of the minimum shift crew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency.

e. The amount of overtime worked by plant staff members performing safety-related functions must be limited in accordance with the NRG Policy Statement on working hours (Generic Letter No. 82-12).

f. The Operations Manager, Operating Engineer, Senior Nuclear Shift Supervisor, and Nuclear Shift Supervisor shall each hold a senior reactor operator license. The Nuclear Control Operators shall hold reactor operator licenses.

The Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of Fire Brigade members provided immediate action is taken to restore the Fire Brigade to within the minimum requirements.

SALEM - UNIT 1 6-2 Amendment No.

Figure 6.2-1 CORPORATE HEADQUARTERS AND OFF-SITE ORGANIZATION FOR MANAGEMENT AND TECHNICAL SUPPORT (Deleted)

SALEM - UNIT 1 6-3 Amendment No.

_J

FIGURE 6.2 - 2 FACILITY ORGANIZATION (Deleted)

SALEM - UNIT 1 6-4 Amendment No.

TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION SALEM UNIT 1 WITH UNIT 2 IN MODES 5 OR 6 OR DE-FUELED POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION MODE3 l, 2, 3 & 4 MODE3 5 & 6 SNSS la SRO none STA none NCO 1 EO/UO 2c Maintenance Electrician none a,e Rad. Pro. Technician 1 WITH UNIT 2 IN MODES 1, 2, 3 OR 4 POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION MODES l, 2, 3 & 4 MODES 5 & 6 SNSS la la SRO lb none STA lb none NCO 2d 1 EO/UO 3 1 Maintenance Electrician la none Rad. Pro. Technician la la

~/ Individual may fill the same position on Unit 2

£/ Individual who fulfills the STA requirement may fill the same position on Unit 2. The STA, if a licensed SRO, may concurrently fill the SRO position on one unit; the other unit also requires a qualified SRO on shift.

£/ One of the two required individuals may fill the position on Unit 2, such that there are a total of three EO/UO's for both units.

d/ One of the three required individuals may fill the same position of Unit 2, such that there are a total of five EO/UO's for both units.

gj Not needed if both reactors are de-fueled.

SALEM - . UNIT 1 6-5 Amendment No.

TABLE 6.2-1 (Continued)

SNSS - Senior Nuclear Shift Supervisor with a Senior Reactor Operator License on both units.

SRO Individual with a Senior Reactor Operator License on both units (normally, a Nuclear Shift Supervisor).

NCO Nuclear Control Operator with a Reactor Operator License on both units.

STA Shift Technical Advisor (if licensed as SRO, may be assigned duties as a Nuclear Shift Supervisor).

EO/UO- Equipment Operator or Utility Operator.

Except for the Senior Nuclear Shift Supervisor, the Shift Crew Composition may be one less than the minimum requirements of Table 6.2-1 for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate the unexpected absence of on-duty shift crew members provided that immediate action is taken to restore the Shift Crew Composition to within the minimum requirements of Table 6.2-1.

This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewperson's being late or absent.

During any absence of the Senior Nuclear Shift Supervisor from the Control Room area while the unit is in any MODE, an individual with a valid SRO License shall be designated to assume the Control Room command function.

SALEM - UNIT 1 6-6 Amendment No.

ADMINISTRATIVE CONTROLS 6.2.3 SHIFT TECHNICAL ADVISOR 6.2.3.1 The Shift Technical Advisor shall serve in an advisory capacity to the Senior Nuclear Shift Supervisor on matters pertaining to the engineering aspects assuring safe operation of the unit.

6.2.3.2 The Shift Technical Advisor shall have a Bachelor's Degree or equivalent in a scientific or engineering discipline with specific training in plant design and response and analysis of the plant for transients and accidents.

6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI Nl8.l-1971 for comparable positions and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRG letter to all licensees, except for the Radiation Protection Engineer or Radiation Protection/Chemistry Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 197S.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be coordinated by each functional level manager (Department Head) at the facility and maintained under the direction of the Manager - Nuclear Training and shall meet or exceed the requirements and recommendations of Section S.S of ANSI Nl8.l-1971 and 10 CFR Part SS.

6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Manager - Site Protection and shall meet or exceed the requirements of Section 27 of NFPA Code-197S, except for Fire Brigade training sessions which shall be held at least quarterly.

SALEM - UNIT 1 6-7 Amendment No.

ADMINISTRATIVE CONTROLS 6.5 REVIEW AND AUDIT

6.5.1 FUNCTION STATION OPERATIONS REVIEW COMMITTEE (SORC) 6.5.1.1 The Station Operations Review Committee shall function to advise the General Manager - Salem Operations on operational matters related to nuclear safety.

COMPOSITION 6.5.1.2 The Station Operations Review Committee (SORC) shall be composed of:

Chairman: General Manager - Salem Operations Member and Vice Chairman: Maintenance Manager Member and Vice Chairman: Operations Manager Member and Vice Chairman: Technical Manager Member: Radiation Protection/Chemistry Manager Member: Radiation Protection Engineer Member: Chemistry Engineer Member: Maintenance Engineers Member: Operating Engineers Member: Technical Engineers (Group Heads)

Member: Onsite Safety Review Engineer ALTERNATES 6.5.1.3 Alternates:

a. Alternates shall be appointed by the SORC Chairman in writing.

b. Only designated Vice Chairmen may act as Chairman of a SORC meeting in the absence of the General Manager - Salem Operations.

c. The Senior Nuclear Shift Supervisor (SNSS) may act as an alternate for the Operations Manager or an Operating Engineer. The SNSS may also act as an alternate when the Operations Manager is acting as Chairman.

MEETING FREQUENCY 6.5.1.4 The SORC shall meet at least once per calendar month and as convened by the SORC Chairman or his designated alternate.

QUORUM 6.5.1.5 The minimum quorum of the SORC necessary for the performance of the SORC responsibility and authority provisions of these technical specifications shall consist of the Chairman or his designated alternate and five members including alternates.

SALEM - UNIT 1 6-8 Amendment No.

ADMINISTRATIVE CONTROLS QUORUM (continued)

a.

b.

No more than two members or one member and one alternate from any individual department will make up part of the voting quorum.

If the Chairman for a meeting is a Vice Chairman, then up to two additional members (or one member and one alternate) may be part of the voting quorum.

RESPONSIBILITIES 6.5.1.6 The Station Operations Review Committee shall be responsible for:

a. Review of: (1) Station Administrative Procedures and changes thereto and (2) Newly created procedures or changes to existing procedures that require a 10CFR50.59 safety evaluation as described in Section 6.5.3.2.d.

b. Review of all proposed tests and experiments that affect nuclear safety.

c. Review of all proposed changes to Appendix "A" Technical Specifications.

d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety .

e.

f.

Review of the safety evaluations that have been completed under the provisions of 10 CFR 50.59.

Initiation or review of investigations of all violations of the Technical Specifications including the reports covering evaluation and recommendations to prevent recurrence.

g. Review of all REPORTABLE EVENTS.

h. Review of facility operations, as determined by the SORC Chairman, to detect potential nuclear safety hazards.

i. Performance of special reviews, investigations or analyses and reports thereon as determined by the SORG.

j. Review of the Facility Security Plan and implementing procedures and changes thereto.

k. Review of the Facility Emergency Plan and implementing procedures and changes thereto that require a 10CFR50.59 evaluation, or involve a potential decrease in the effectiveness of the plan, per 10CFR50.54(q). as described in Section 6.5.3.2.d.

1. Review of the Fire Protection Program and implementing procedures and changes thereto that require a 10CFR50.59 safety evaluation.

SALEM - UNIT 1 6-9 Amendment No.

ADMINISTRATIVE CONTROLS RESPONSIBILITIES (continued)

m.

n.

Review of all unplanned on-site releases of radioactivity to the environs including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence.

Review of changes to the PROCESS CONTROL MANUAL and the OFF-SITE DOSE GALGUIATION MANUAL.

SORG REVIEW PROCESS 6.5.1.7 A technical review and control system utilizing qualified reviewers shall function to perform the periodic or routine review of procedures and changes thereto. Details of this technical review process are provided in Section 6.5.3.

AUTHORITY 6.5.l.8 The Station Operations Review Committee shall:

a. Provide recommendations to the General Manager - Salem Operations, indicating written approval or disapproval of items considered under 6.5.1.6 above.

b. Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Vice President and Chief Nuclear Officer and the General Manager - Quality Assurance and Nuclear Safety of disagreement between the SORG and the General Manager - Salem Operations; however, the General Manager

- Salem Operations shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

RECORDS AND REPORTS 6.5.1.9 The Station Operations Review Committee shall maintain written minutes of each meeting and copies shall be provided to the Vice President and Chief Nuclear Officer, the General Manager - Quality Assurance and Nuclear Safety and the Manager - Nuclear Safety.

6.5.2 NUCLEAR SAFETY REVIEW FUNCTION 6.5.2.1 The Nuclear Safety Department shall function to provide the independent safety review program and audit of designated activities.

COMPOSITION 6.5.2.2 The Nuclear Safety Department, under the cognizance of the General Manager - Quality Assurance and Nuclear Safety, shall consist of the Manager -

Nuclear Safety, the Offsite Safety Review staff (OSR) and the Onsite Safety Review Group (SRG). The OSR staff and the SRG each consist of at least four dedicated, full-time engineers.

SALEM - UNIT 1 6-10 Amendment No.

ADMINISTRATIVE CONTROLS COMPOSITION (continued)

The Manager - Nuclear Safety and the Offsite Safety Review staffshall meet or exceed the qualifications described in Section 4.7 of ANS 3.1 - 1981 and shall be guided by the provisions for independent review described in Section 4.3 of ANSI Nl8.7 - 1976 (ANS 3.2).

The Offsite Safety Review staff shall generally possess experience and competence in the areas listed in Section 6.5.2.4.1. A system of qualified reviewers from other technical organizations may be used to augment OSR staff expertise in the disciplines of Section 6.5.2.4.1, where appropriate. Such qualified reviewers shall meet the same qualification requirements as the Offsite Safety Review Staff, and shall not have been involved with performance of the original work.

The Onsite Safety Review Group staff shall meet or exceed the qualifications described in Section 4.4 of ANS 3.1 - 1981.

CONSULTANTS 6.5.2.3 Consultants or other technical experts shall be utilized by the Nuclear Safety Department to the extent necessary.

6.5.2.4 OFF-SITE SAFETY REVIEW (OSR)

FUNCTION 6.5.2.4.1 The OSR staff shall function to provide independent review and audit of designated activities in the areas of:

a. Nuclear Power Plant Operations

b. Nuclear Engineering

c. Chemistry and Radiochemistry

d. Metallurgy

e. Instrumentation and Control

f. Radiological Safety

g. Mechanical Engineering

h. Electrical Engineering

i. Quality Assurance j . Nondestructive Testing

k. Emergency Preparedness SALEM - UNIT 1 6-11 Amendment No.

ADMINISTRATIVE CONTROLS REVIEW 6.5.2.4.2 The OSR shall review:

a. The safety evaluations for changes to procedures, equipment, or systems; and tests or experiments completed under the provisions of 10CFR50.59, to verify that such actions did not constitute an unreviewed safety question;

b. Proposed changes to procedures, equipment, or systems; and tests or experiments that involve an unreviewed safety question as defined in lOGFRS0.59;

c. Proposed changes to Technical Specifications or to the Operating License;

d. Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance;

e. Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety;

f. All REPORTABLE EVENTS;

g. All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety-related structures, systems or components that could affect nuclear safety;

h. Reports and meeting minutes of the Station Operations Review Committee.

AUDITS 6.5.2.4.3 Audits of facility activities shall be performed under the cognizance of the OSR staff. These audits shall encompass:

a. The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.

b. The performance, training, and qualifications of the entire facility staff at least once per 12 months.

c. The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems, or method of operation that affect nuclear safety at least once per 6 months.

d. The performance of activities required by the Operational Quality Assurance Program to meet the Criteria of Appendix B to 10CFR50, at least once per 24 months.

e. The Facility Emergency Plan and implementing procedures at least once per 12 months.

SALEM - UNIT 1 6-12 Amendment No.

ADMINISTRATIVE CONTROLS AUDITS (continued)

f.

g.

The Facility Security Plan and implementing procedures at least once per 12 months.

Any other area of facility operation considered appropriate by the General Manager - Quality Assurance and Nuclear Safety or the Vice President and Chief Nuclear Officer.

h. The Facility Fire Protection Program and implementing procedures at least once per 24 months.

i. The fire protection and loss prevention program implementation at least once per 12 months utilizing either a qualified offsite licensee fire protection engineer(s) or an outside independent fire protection consultant. An outside independent fire protection consultant shall be utilized at least once per 36 months.

j. The radiological environmental monitoring program and the results thereof at least once per 12 months.

The above audits may be conducted by the Quality Assurance Department or an independent consultant. Audit plans and final audit reports shall be reviewed by the OSR staff.

RECORDS AND REPORTS 6.5.2.4.4 Records of OSR activities shall be maintained. Reports of reviews and audits shall be prepared and distributed as indicated below:

a. The results of reviews performed pursuant to Section 6.5.2.4.2 shall be reported to the Vice President and Chief Nuclear Officer at least monthly.

b. Audit reports prepared pursuant to Section 6.5.2.4.3 shall be forwarded by the auditing organization to the Vice President and Chief Nuclear Officer and to the management positions responsible for the areas audited (1) within 30 days after completion of the audit for those audits conducted by the Quality Assurance Department, and (2) within 60 days after completion of the audit for those audits conducted by an independent consultant.

6.5.2.5 ON-SITE SAFETY REVIEW GROUP (SRG)

FUNCTION 6.5.2.5.1 The Onsite Safety Review Group (SRG) shall function to provide: the review of plant design and operating experience for potential opportunities to improve plant safety; the evaluation of plant operations and maintenance activities; and advice to management on the overall quality and safety of plant operations.

The SRG shall make recommendations for revised procedures, equipment modifications, or other means of improving plant safety to appropriate station/ corporate management.

SALEM - UNIT 1 6-13 Amendment No.

ADMINISTRATIVE CONTROLS RESPONSIBILITIES

6.5.2.5.2 a.

The SRG shall be responsible for:

Review of selected plant operating characteristics, NRC issuances, industry advisories, and other appropriate sources of plant design and operating experience information that may indicate areas for improving plant safety.

b. Review of selected facility features, equipment, and systems.

c. Review of selected procedures and plant activities including maintenance, modification, operational problems, and operational analysis.

d. Surveillance of selected plant operations and maintenance activities to provide independent verification* that they are performed correctly and that human errors are reduced to as low as reasonably achievable.

AUTHORITY 6.5.2.6 The Nuclear Safety Department shall report to and advise the Vice President and Chief Nuclear Officer on those areas of responsibility specified in Sections 6.5.2.4 and 6.5.2.5.

6.5.3 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.3.1 Programs required by Technical Specification 6.8 and other procedures which affect nuclear safety as determined by the General Manager - Salem Operations, other than editorial or typographical changes shall be reviewed as follows:

PROCEDURE RELATED DOCUMENTS 6.5.3.2 Procedures, Program and changes thereto shall be reviewed as follows:

a. Each newly created procedure, program or change thereto shall be independently reviewed by an individual knowledgeable in the subject area other than the individual who prepared the procedure, program or procedure change, but who may be from the same organization as the individual/group which prepared the procedure or procedure change. Procedures other than Station Administrative procedures will be approved by the appropriate Station Department Manager or by the General Manager - Salem Operations. Each Station Department Manager shall be responsible for a predesignated class of procedures. The General Manager - Salem Operations shall approve Station Administrative Procedures, Security Plan implementing procedures and Emergency Plan implementing procedures .

Not responsible for sign-off function SALEM - UNIT 1 6-14 Amendment No.

ADMINISTRATIVE CONTROLS

b. On-the-spot changes to procedures which clearly do not change the intent of the approved procedures shall be approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator License. Revisions to procedures which may involve a change in intent of the approved procedures, shall be reviewed in accordance with Section 6.5.3.2.a above.

c. Individuals responsible for reviews performed in accordance with item 6.5.3.2a above shall be approved by the SORC Chairman and designated as Station Qualified Reviewers. A system of Station Qualified Reviewers, each of whom shall possess qualifications that meet or exceed the requirements of Section 4.4 of ANSI Nl8.l - 1971, shall be maintained by the SORG Chairman. Each review shall include a written determination of whether or not additional cross-disciplinary review is necessary. If deemed necessary, such review shall be performed by the appropriate designated review personnel.

d. If the Department Manager determines that the documents involved require a 10CFRS0.59 safety evaluation, the documents shall be forwarded for SORC review and also to the OSR staff for an independent review to determine whether or not an unreviewed safety question is involved. Pursuant to 10CFRS0.59, NRC approval of items involving unreviewed safety questions or Technical Specification changes shall be obtained prior*to implementation.

NON-PROCEDURE RELATED DOCUMENTS 6.5.3.3 Tests or experiments, changes to Technical Specifications, and changes to equipment or systems shall be forwarded for SORC review and also to the OSR staff for an independent review to determine whether or not an unreviewed safety question is involved. The results of the OSR staff reviews will be provided to SORG. Recommendations for approval are made by SORC to the General Manager - Salem Operations. Pursuant to 10CFRS0.59, NRC approval of items involving unreviewed safety questions or requiring Technical Specification changes shall be obtained prior to implementation.

RECORDS AND REPORTS 6.5.3.4 Written records of reviews performed in accordance with item 6.5.3.2a above, including recommendations for approval or disapproval, shall be maintained. Copies shall be provided to the General Manager - Salem Operations, SORC, the OSR staff and/or NRC as necessary when their reviews are required.

6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a. The Commission shall be notified and/or a report submitted pursuant to the requirements of Section 50.73 to 10CFR Part 50, and

b. Each REPORTABLE EVENT shall be reviewed by the SORC and the resultant Licensee Event Report submitted to the OSR staff and the Vice President and Chief Nuclear Officer.

SALEM - UNIT 1 6-15 Amendment No.

ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a. The unit shall be placed in at least HOT STANDBY within one hour.

b. The NRG Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Vice President and Chief Nuclear Officer and General Manager - Quality Assurance and Nuclear Safety shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the SORG. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

d. The Safety Limit Violation Report shall be submitted to the Commission, the General Manager - Quality Assurance and Nuclear Safety and the Vice President and Chief Nuclear Officer within 14 days of the violation.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.

b. Refueling operations.

c. Surveillance and test activities of safety related equipment.

d. Security Plan implementation.

e. Emergency Plan implementation.

f. Fire Protection Program implementation.

g. PROCESS CONTROL PROGRAM implementation.

h. OFFSITE DOSE CALCULATION MANUAL implementation.

i. Quality Assurance Program for effluent and environmental monitoring.

6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed and approved in accordance with Specification 6.5.l.6 or 6.5.3, as appropriate, prior to implementation and reviewed periodically as set forth in administrative procedures.

SALEM - UNIT 1 6-16 Amendment No.

ADMINISTRATIVE CONTROLS 6.8.3 On-the-spot changes to procedures of 6.8.1 above may be made provided:

a.

b.

The intent of the original procedure is not altered.

The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.

c. The change is documented and receives the same level of review and approval as the original procedure under Specification 6.5.3.2a within 14 days of implementation.

6.8.4 The following programs shall be maintained:

a. Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include (recirculation spray, safety injection, chemical and volume control, gas stripper, recombiners, ... ). The program shall include the following:

(i) Preventative maintenance and periodic visual inspection requirements, and (ii) Integrated leak test requirements for each system at refueling cycle intervals or less.

b. In-Plant Radiation Monitoring A program which will ensure the capability to accurately determine the airborne iodine concentration in areas under accident conditions. This program shall include the following:

(i) Training of personnel, (ii) Procedures for monitoring, and (iii) Provisions for maintenance of sampling and analyses equipment.

c. Secondary Water Chemistry A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation. This program shall include:

(i) Identification of a sampling schedule for the critical variables and the control points for these variables, (ii) Identification of the procedures used to measure the values of the critical variables, (iii) Identification of process sampling points, including monitoring at the discharge of the condensate pumps for evidence of condenser in-leakage.

SALEM - UNIT 1 6-17 Amendment No.

ADMINISTRATIVE CONTROLS (iv) Procedures for the recording and management of data,

(v) Procedures defining corrective actions for off-control-point chemistry conditions, (vi) A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.

d. Backup Method for Determining Subcooling Margin A program which will ensure the capability to accurately monitor the Reactor Coolant System Subcooling Margin. This program shall include the following:

(i) Training of personnel, and (ii) Procedures for monitoring

e. Postaccident Sampling A program* which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions. The program shall include the following:

(i) Training of personnel (ii) Procedures for sampling and analysis, (iii) Provisions for maintenance of sampling and analysis equipment .

It is acceptable if the licensee maintains details of the program in plant operation manuals.

SALEM - UNIT 1 6-18 Amendment No.

ADMINISTRATIVE CONTROLS 6.9 REPORTING REQUIREMENTS

ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the USNRC Administrator, Region 1, unless otherwise noted.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

ANNUAL REPORTS

6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year.

A single submittal may be made for a multiple unit station. The submittal

should combine those sections that are common to all units at the station.

SALEM - UNIT 1 6-19 Amendment No.

ADMINISTRATIVE CONTROLS 6.9.1.5 Reports required on an annual basis shall include:

a. A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their *ssociated man rem exposure according to work and job functions, e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling.

The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

b. The complete results of steam generator tube inservice inspections performed during the report period (reference Specification 4.4.5.5.b).

c. The results of any specific activity analyses in which the primary coolant exceeded the limits of Specification 3.4.8. The following information shall be included: (1) Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior .to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while the limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than the limit. Each result should include date and time of sampling and the radioiodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.

MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555 with a copy to the USNRC Administrator, Region 1, no later than the 15th of each month following the calendar month covered by the report.

This tabulation supplements the requirements of section 20.407 of 10 CFR Part 20.

SALEM - UNIT 1 6-20 Amendment No.

ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT*

6.9.1.7 Routine Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.

The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies with operational controls (as appropriate), and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.

The reports shall also include the results of land use censuses required by Specification 3.12.2. The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all measurements taken during the period pursuant to the Table and Figures in the environmental radiation section of the ODCM; as well as summarized and tabulated results of locations specified in these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.

The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a summary description of the radiological environmental monitoring program; at least two legible maps, one covering sampling locations near the SITE BOUNDARY and a second covering the more distant locations, all keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program, required by Specification 3.12.l; and discussion of all analyses in which the LLD required by Table 4.12-1 was not achievable.

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT*

6.9.1.8 Routine Radioactive Effluent Release Reports covering the operation of the unit during the previous six months of operation shall be submitted within 60 days after January 1 and July 1 of each year.

The Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21. "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of

A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

SALEM - UNIT 1 6-21 Amendment No.

ADMINISTRATIVE CONTROLS Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a

quarterly basis following the format of Appendix B thereof.

The Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured),

or in the form of joint f*equency distributions of wind speed, wind direction, and atmospheric stability . This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 5.1-3) during the report period.

All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCUIATION MANUAL.

The Radioactive Effluent Release Report to be submitted 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.

The Radioactive Effluent Release Reports shall include the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped offsite during the report period:

a. Container volume,

b. Total curie quantity (specify whether determined by measurement or estimate),

c. Principal radionuclides (specify whether determined by measurement or estimate),

d. Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),

In lieu of submission with the first half year Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRG upon request.

SALEM - UNIT 1 6-22 Amendment No.

ADMINISTRATIVE CONTROLS

e. Type of container (e.g., LSA, Type A, Type B, Large Quantity), and

f. Solidification agent or absorbent (e.g., cement, urea formaldehyde).

The Radioactive Effluent Release Reports shall include a list of descriptions of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.

The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification 3.12.2.

RADIAL PEAK.ING FACTOR LIMIT REPORT RTP 6.9.1.9 The F limits for Rated Thermal Power (F ) for all xy xy core planes containing bank "D" control rods and all unrodded core planes and the plot of predicted heat flux hot channel factor times relative power

.<F~*PREL) vs. Axial Core Height with the limit envelope shall be provided to the NRC Document Control Desk with copies to the Regional Administrator and the Resident Inspector. The Report shall be provided to the Commission no later than thirty days subsequent to initial use of F limits for xy surveillance unless otherwise approved by the Commission by letter.

In addition, in the event that the limit should change, requiring a new submittal or an amended submittal to the Peaking Factor Limit Report, it will be submitted within thirty days of the date the limit would become effective unless otherwise approved by the Commission by letter.

RTP Any information needed to support F will be by request from the NRC and xy need not be included in this report.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555 with a copy to the Administrator, Region 1, within the time period.specified for each report.

6.10 RECORD RETENTION In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated .

SALEM - UNIT 1 6-23 Amendment No.

ADMINISTRATIVE CONTROLS RECORD RETENTION (continued) 6.10.1 The following records shall be retained for at least five years:

a. Records and logs of unit operation covering time interval at each power level.

b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

c. All REPORTABLE EVENTS submitted to the Commission.

d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

e. Records of changes made to Operating Procedures required by Specification 6.8.1.

f. Records of radioactive shipments.

g. Records of sealed source and fission detector leak tests and results.

h. Records of annual physical inventory of all sealed source material of record.

6.10.2 The following records shall be retained for the duration of the Unit Operating License:

a. Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report.

b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

c. Records of radiation exposure for all individuals entering radiation control areas.

d. Records of gaseous and liquid radioactive material released to the environs.

e. Records of transient or operational cycles for those facility components identified in Table 5.7-1.

f. Records of reactor tests and experiments.

g. Records of training and qualification for current members of the plant staff.

h. Records of in-service inspections performed pursuant to these Technical Specifications .

i. Records of Quality Assurance activities required by the QA Manual.

SALEM - UNIT 1 6-24 Amendment No.

ADMINISTRATIVE CONTROLS

j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10CFR50.59

k. Records of SORG meetings and acivities of OSR (and meetings of its predecessor, the Nuclear Review Board).

1. Records for Environmental Qualification which are covered under the provisions of Paragraph 6.16.

m. Records of the service lives of all hydraulic and mechanical snubbers including the date at which the service life commences and associated installation and maintenance records.

n. Records of secondary water sampling and water quality.

o. Records of analyses required by the radiological environmental monitoring program which would permit evaluation of the accuracy of the analysis at a later date. This should include procedures effective at specified times and QA records showing that these procedures were followed.

6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.l In lieu of the "control device" or "alarm signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20, each high radiation area in which the int*nsity of radiation is greater than 100 mremjhr but less than 1000 mremjhr shall be barricaded and conspicuously posted as a High Radiation Area and en~*ance thereto shall be controlled by issuance of a Radiation Exposure Permit . If the high radiation area is established for a period of 30 days or less, direct surveillance to prevent unauthorized entry may be used instead of the access controls described above, per 10CFR20.203(c)(2)(iii)(4). Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring device which continuously indicates the radiation dose rate in the area.

This is normally defined as the level at a distance of 18 inches from the source or accessible surface.

- Radiation Protection personnel or personnel escorted by Radiation Protection personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided that they are otherwise following plant radiation protection procedures for entry into high radiation areas.

SALEM - UNIT 1 6-25 Amendment No.

ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (continued)

b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.

c. A health physics qualified individual (i.e., qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Radiation Work Permit.

6.12.2 In addition to the requirements of 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose greater than 1000 mrem shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Senior Nuclear Shift Supervisor on duty and/or Senior Supervisor - Radiation Protection. Doors shall remain locked except during periods of access by personnel under an approved Radiation Work Permit which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area. For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose in excess of 1000 mrem that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonable constructed around the individual areas, then that area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device. In lieu of the stay time specification of the RWP, direct or remote (such as use of closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.

6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.

6.13.2 Licensee initiated changes to the PCP:

1. Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change(s) was made. This submittal shall contain:

a. Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information;

This is normally defined as the level at a distance of 18 inches from the source or accessible surface.

SALEM - UNIT 1 6-26 Amendment No.

ADMINISTRATIVE CONTROLS PROCESS CONTROL PROGRAM (continued)

b.

c.

A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and Documentation of the fact that the change has been reviewed and found acceptable by the SORG.

2. Shall become effective upon review and acceptance by the SORG.

6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.l The ODCM shall be approved by the Commission prior to implementation.

6.14.2 Licensee initiated changes to the ODCM:

1. Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change(s) was made. This submittal shall contain:

a. Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information. Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change(s);

b. A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determination; and

c. Documentation of the fact that the change has been reviewed and found acceptable by the SORG.

2. Shall become effective upon review and acceptance by the SORG.

6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID. GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 6.15.l Licensee initiated major changes to the radioactive waste system (liquid, gaseous and solid):

1. Shall be reported to the Commission in the UFSAR for the period in which the evaluation was reviewed by (SORG). The discussion of each change shall contain:

a. A summary of the evaluation that led to the determination that the change could be made in accordance with 10CFRS0.59; SALEM - UNIT 1 6-27 Amendment No.

ADMINISTRATIVE CONTROLS MAJOR CHANGES TO RADIOACTIVE LIQUID. GASEOUS AND SOLID WASTE TREATMENT SYSTEMS (continued)

b. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;

c. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems;

d. An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto;

e. An evaluation of the change, which shows the expected maximum exposures to individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto;

f. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made;

g. An estimate of the exposure to plant operating personnel as a result of the change; and

h. Documentation of the fact that the change was reviewed and found acceptable by the (SORG).

2. Shall become effective upon review and acceptance by the SORG.

SALEM - UNIT 1 6-28 Amendment No.

ADMINISTRATIVE CONTROLS 6.16 ENVIRONMENTAL QUALIFICATION 6.16.1 All safety-related electrical equipment in the facility shall be qualified in accordance with the provisions of: Division of Operating Reactors "Guidelines for Evaluating Environmental Qualification of Class lE Electrical Equipment in Operating Reactors" (DOR Guidelines); or, NUREG-0588 "Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment," December 1979. Copies of these documents are attached to Order for Modification of License No. DPR-70 dated October 24, 1980.

6.16.2 Complete and auditable records shall be available and maintained at a central location which describe the environmental qualification method used for all safety-related electrical equipment in sufficient detail to document the degree of compliance with the DOR Guidelines or NUREG-0588. Such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified.

SALEM - UNIT 1 6-29 Amendment No.

UNIT 2 MARKUP PAGES

INOEX DEFINITIONS SECTION 1.0 *DEFINITIONS DEJ'INED TERMS * * * * * * * * * * * * * * * * * * * * * *

l-l ACTION * * * * . * * * * * * * *

I * * * * * * * * * * * *

l-1 AXIAL FlUX OIFFEREHC! * * * * * * * * * * * * * * * * * *

1-1 CHANNEL CALIBRATION * * * * * * * * * * * * * * * * * * *

1-1 OfAltNEI. at ECX * * ** * * * * *. * * * * * * * * * * * * * *

1-1 CHANNEL FUNCTI OHAL T'EST * * * * * * * * * * * * * * * * *

1-1 CONTAINMEMT INTEGRITY * * * * * * * * * * * * * * * * * *

1-2 CONnOLLED t.i.AKAGE * * * * * * * * * * * * * * * * * * * *

1-2 CORE ALTERATION * * * * * * * * * * * * * * * * * * * * *

1-2 DOSE EQUIVAL!11T I-131 * * * * * * * * * * * * * * * * * *

l-2

!-AVERAGE DISINTEGRATION ENERGY * * * * * * * * * * * * *

1-3 ENGINEERED SAFETY F!ATURE RESPONSE TIME * * * * * * * * *

1-3 FREQUENCY NOTATION * * * * * * * * * * * * * * * *

1,.3 GASEOUS RAOWASTE TREATMEKT' SYSTEM. * * * * * * * * * * * *

1-3 IDEMTIFIEO WXAGE * * * * * * * * * * * * * * * * * * * *

1-3 MEMBER( S) Of THE PUBLIC. * * * * * * * * * * * * * * * * **

1-4 OF1SIT! COSE CALCULATION l"ANUAL (ODCM) * * * * * * * * * *

l-4 OPERABLE

OPERAS IL ITY * * * * * * * * * * * * * * * ** * *

1-4 OPERATIONAL /llJDE * * * * * * * * * * * * * * * * * * * * *

1-4 PHYSICS T'ESTS * * * * * * * * * * * * * * * * * * * * * *

1-5 PRESSURE BOUNDARY L!AXAGE. * * * * * * * * * * * * * * * *

1-5 PROCESS CONTROL PROGRAM (PCP) * * * * * * * * * * * * * * *

PURGE-PURGING * * * * * * * * * * * * * * * * * * * * * *

QUAORAlfT POWER TILT RATIO * * * * * * * * * * * * * * * *

1-5 1-5 1-5 f

RATiD TI4ERMAL POWER * * * * * * * * * * * * * * * * * * *

1-5 REACTOR TRIP SYSTEM RESPONSE TIME * * * * * * * * *

1-o REPORTABLE '<<atRREME!>-2. * * * * * * * * * * * * * * * * *

1-o SHUTDOWN MARGIN. * * * * * * * * * * * * *

SIT! BOUNDARY * * * * * * * * * * * * * * * * *

SOLIDIFICATION * * * * * * * * * * * * *

SOURCE 04ECX * * * * * * * * * * * * * * *

STAGGERED Ts:ST BASIS

TMERMAL PfJW!R 1-6 1-o 1-o l-6 1-o 1-7 r

r UNIDENTIFIED ~EAICAGE * * * * * * * * * * * * * * * * * * *

1-7 UNRESTRicm AREA' * * * * * * * * * * * * * * * * * *

1-7 VENTILATION EXHAUST TREATMENT SYST!M * * * * * * * * *

l-7 VEMT! NS * * * * * * * * *.* * * * * * * * * * * * * *

1-7 r

SALEM

UNIT 2 I Amet1dment No.

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY ..................... 6-1 6.2 ORGANIZATION Onsite and Offsite Organization 6-1 Faci 1i ty Staff . . 6-1 Shift Technical Advisor 6-%7 6.3 FACILITY STAFF QUALIFICATIONS 6-fi 7 6.4 TRAINING . . . . 6-~7 6.5 REVIEW AND AUDIT 6.5.1 STATION OPERATIONS REVIEW COMMITTEE Function . . . . 6-/(~

Composition . . . 6-;/ g Alternates 6-;f <g Meeting Frequency 6-;f B Quorum . . . . . 6-;f 8 Responsibilities 6-.$ 9

~Review Process . 6-210

Authority . . . . 6-J.f /0 0J f2epoy Record~ . . . . . 6-$/Cl 6.5.2 NUCLEAR SAFETY REVIEW Function . . . . . . 6-fJ ,0 Composition . . . . . 6-g' !C>

Consultants . . . . . . . . 6-S-S. I/

r----::k'ff-Site Review ~ @$8-). 6-Sfi-//

evi ew . . . . . . . . . . 6-'9-a- /~

udi ts . . . . . . . . . . . . . 6 /;;;2.

--n-Si te Safety Review Group {51Z~). 6-'.H:-13 esponsibil ities 6-1-:l. I Authority . . . . . . . . . . . . 6-H-/'f C-13 1

~ . ~-II SALEM - UNIT 2 XVIII Amendment No.

ADMINISTRATIVE CONTROLS

=============================================================

SECTION PAGE 6.5.3 TECHNICAL REVIEW AND CONTROL . 6-.M' lb° 6.6 REPORTABLE EVENT ACTION

6-J,.2cr IS-6.7 SAFETY LIMIT VIOLATION 6-µ15' 1£ 6.8 PROCEDURES AND PROGRAMS

6-.)-3' /6 6.9 REPORTING REQUIREMENTS 6.9.l ROUTINE REPORTS 6-16 19 6.9.2 SPECIAL REPORTS 6-X ~3 6.10 RECORD RETENTION 6 -,21'" -;;;? .3 6.11 RADIATION PROTECTION PROGRAM 6-$2S-6.12 HIGH RADIATION AREA . . . . . 6-~~:;-

6.13 PROCESS CONTROL PROGRAM .

6~-;;2C 6.14 OFFSITE DOSE CALCULATION MANUAL 6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS . . . . * .

SALEM - UNIT 2 XIX Amendment No.

. OEFtNIT!ONS REACiOR TRIP SYSTEM RESPONSE TIME l.25 Th* REACTOR TRIP SYST!M RESPONSE TIME shall be the time interval from when th* 111Qn1tored parameter exceeds 1ts trip s*tpo1nt at the channel sensor until loss of stationary gr1pp*r ca11 voltag*.

REPORTABLE t.27 A REPORTABt..E shall be 1ny of thosa cand1t1ons spec1f1ed 1n

@iC1f1cal1ont S.9a.a: and 5.9.l.be-

-L @;ori so~ 73 To /OC PR.. Pqr 1- 525)

SMUTtJOWH MARGIN l.28 SHUTtlOWH MARGIN shall be th* instantaneous amount of reactivity by. which th* reactor 1s subcr1t1cal or would be subcr1t1cal tram its pres*nt cand1t1on assuming all full l*ngtn rad clustar assenblits (shutdown 111d control) ar* fully 1nsartld 1xcl$Jt for th* s1ngl* rad cluster assenbly of highest r9act1vity worth wh1c:h 1s assumed ta b9 fully withdrawn.

( SIT£ BOUNDARY l.29 ih* stn BOUNDARY shall be that Hn* b9yond wh1dl th* land is not owned, leased, or oth*n.1sa cantr"Q119d by th* 11c1ns1e, as sha-n in Figure 5.l-3, and wh1dl daf1nes th* uclus1oil 1~1 as shewn 1n F1gun S.l-l.

SOLIDIF!CAT!ON l.30 SOLIDIFICAT!ON shall be the canvel"'S1on of wet rad1aact1ve wastes into a farm that meets sh1pp1ng and burial gr"Qund requ1renents.

SOURCE CHECX l.31 SOURCE CHECX shall b* th* qua11tat1ve assessment of channel responsa when the channel s*nsor is expos9d ta a sourca of 1nc1"9asad rad1oact1v1ty.

STAGGCRED T'ESi BASIS l.32 *A STAGGERED* TEST BASIS ~h11 cans1st of:

1n) a: A test schedule far syst!lllS, subsystems, trains, ar other des1gnate<i comQonents abta1ned by d1v1d1ng the spec1f1e<1 test interval 1nt~,.l, equal subintet"'Vals, cw SAW - UNtT Z l-5 Amendment No.

~£~ O!~IBUT!OH ~!~!iS 4.%.%. 1 The p~visions of ~ec1f1~t1an 4.0.4 &l""I not ~li~le.

* * .Z.%.Z Fry snal1 b* eval~t.d to data-r"Sine 11 Fq(Z) fs witniii fU lf*it by~

1. Using t."le movaa11 inc=T"'t d*~~,., to cetain a p~r df stributian

~ at any ntE?Jl.AL. ~ gl"Utar tAM S: Qf AATIII TMEPJIAL. P<l'ti'E~.

b. Incnasi"9 the MUUMd Fr/ ~nent o1 t.M "'*-'" distrfbutian a; tsy : to &ccunt for aanut'~ctl.ll"i ni; t.o 1erancas ind f1.1rtne r i ncrus i ng UI* '4a1ue by !: ~ ac=unt fol" *uu'"1!Mft't t.incart.aimies.

c. ~~ari~g Ule Fxy c*ut1d (~) ocuined in b, &Cove ~:

l. The Fry 1iaiu fof' RATEQ TMUJi'AL ~ CF~) for the 1;1;t"C-priau Mu um c=" planes ;iY1n in 1. and f., below, and

z. ihe T""tl&tionsnip:

F.; *~Cl *el-9)]

wtter-e Fz,L '.s the 1iait r~r f1"1ctiwl TM£~!. PO\fU 0;:11r1tian f

e.x;u-.ss<.:': :s a f\lltC'tion of ~ and P 1s the fraction af AAT!D

'T'M.E~L. ~~ at wni i:.i F'z::J wu *asu1"'9d.

d. R~1suring Frt ac:=rdint; to t.~* followiMq sc~edu11:

1. 'ta\en F~ is gl"Htar t:lan t.~* F~ tiait for t."I* i;~M~r-i ata

.. 1su~ ;=.., pl.,,* bu~ less tA&n UI* F L l""tl&tianshiQ, &ddi-tianal ~o-.r- distribution &1;1s sh.All bit ~kan and F~ i:-=mo~r~~

t4 F.fr~ and F I.*

rt rt'

) Ei tl'let" within %4 houn &fur UCHdin~ ?)y za.: =f ~n~

TH£ml. PO'#Ei =1" . ~Mlbl", ~* nt£?Jl.AL. pew£R &'t 'tffti c:i FxyC

'tf<IS l ut ~t.ani n~d. 01" SAl...E.11

UHii Z 3/4 Z*~ Amendment No ~

. p~ER OISTRIBUTtOM t.IMiiS

SURVEit.LAHC! REquIREMENTS (Continued) ti) At l 11st ona l'*I" 31 EFPO, wh1 ch1ver occurs f 1nt.

%. Wl'IM th* F~ fs l~s thu _Ot' equ1l t:r the ~ 1fll'lt far th*

appropriate m1sund ca.-. phne, add1t1on1l PGW*r d1str1but1on

. C: ID t.

maps shall be- Uklft and Fq ecmpam to Fq and Fq at l 11st anca per 31 EFPO'.

- Tb* Fq 11111i far RATED THEUW. PCWEI (F~) sull ~ providld for all ca.-. phnu =*taf ning bank -U~ cantrGl M:ids and 111 un1912dd1d co.-. plana fn a Radial Puking .Facto.- L11111t R~ort per

_ spec1f1at1on 1.9.1~

f. Tbe Fq lf111ts of *** *"** an not 1Pl11fc:Ule 111 the fo.11 awing co..-. plane r991ons as~ 111 percant of can h*fgh't fraa the

- bottam of the fuel:

1. Lawer cor. r.g~on fraa OS ta 151, 1nclus1ve.

Z. Upper cant region fra1 SSS to lOOS, 1nclus1ve.

3.. arid plane regions at 17 .n

2S, 3%.1 + 2S, 46.4~

2S, 60.51 + ZS and 74.~ +*zi. inclusive.

4. Corw.plane 1"9tians within* zi of car. height(*

- z.as about th* bank d1mnd pos1t1on of the ban& *n* cant~l reds.

inches)

g. Ev11uat1ng the 1fftcts cf Fq ~ Fq (I) to ~t1rmf n* 11' Fq (Z) fs wtt!l1n tu 111111-t .taenever Fq ucn<ts FX1.

4.2.Z.l Wh*n Fq(Z') 1s ri.Hund pursuant to spec1ffc:at1on 4.10.z.2. an averall rnusured FQ(Z) shall be obtain.ct frm a pcw*r d1 str1but1an map and .1nc:r~ased by

~ to i<<ount for- anufactur1 ng tal erancas and furth*r 1ncn~s~ by SS ta ac:caunt far mm*su~ni unc1rtainty *

SALEM - UM IT Z 3/4 Z-7 Amendment No.~

INSTRUMENTATION RAOIOACTIVE LIOUIO EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDIT.ION FOR OPERATION -*

3.3.3.8 The radioactive lfqufd effluent man1tor1ng fnstrumentatfon channels shown in Table 3.3-12 shall be OPERABLE with the1~ alarm/trip setpofnts set to ensure that the limits of Spec1ffcatfon 3.11.1.1 are not exceeded. The alal"'ll/trfp setpof nts of these channels shall be determined 1n accordance with the OFFSIT£ COSE CALCULATION MANUAL (OOCM)..

APPLICABILITY: *At all.tf1119s.

ACTION:

1. With 1 rad1oact1ve lfquf d effluent 1110nftor1ng f nstrumentatf on channel alann/tr1p setpofnt less conservative than r1qu1red by th* above specff1cation, without delay suspend th* release of radioactive lfquid effluents monitored by th* affecttd channel or decla.-. the channel inoperable or ch1nge th* setpof nt so ft fs acceptably conservative *

. b. Wfth less than th* nrtninun ru.111ra*r of radioactive Hqufd effluent monitoring instrumentation chann*ls OPERABLE, take the ACTION shown fn Table 3.3-12. Exert O.st efforts to return th* fnstrwn1nt to op1rable status within 30 days and, ff unsu~cessful, explain fn th~ next semi-annual radioacth* effluent release niport why th* 1nop*rab11fty was not corrected 1n a tili91y manner.

c. The 11rov1sions of Specifications 3.0.3,,~ (i"f.1.9.(are not applicable. '\

SURVEILLANCE REQUIREMENTS 4.3.3.8 Each radioactive liquid effluent monitoring fnstrwn1ntatfon channel shall b* d1111anstrated OPERABL! by IJ*rformance of th* CHANNEl. CHECX, SOURCE

.04ECX, CHANNEl. CALIBRATION, and CHANNEl. FUNCTIONAL T'EST operations at the frequencies ShO'lll'I in Table 4.3-12.

SALEM - UNIT Z 3/4 3-53 Amendment No.~*

INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive gaseous effluent rronitoring instrumentation channels shown in Table* 3.3-13 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 3.11.2.l are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with the

)ODCM~

APPLICABILITY: As shown in Table 3.3-13 ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification.

without delay suspend the release of radioactive gaseous

effluents monitored by the affected channel or declare the channel inoperable or change the setpoint so it is ac~eptably conservative.

b. With less than the mini1T1Jm number of. radioactive gaseous effluent monitoring instrumentation channels O~ERABLE.

take the ACTION shown in Table 3.3-13. Exert best efforts to return the instrument to operable status within 30 days and, if unsuccessful. explain in the next semi-annual radioactive effluent release report why the inoperability was not corrected in a* timely manner.

c. The provisions of Specifications 3.0.3~~

6:.9.1,9,1:1.. are not appHcable. ie SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive gaseous effluent ITl)nitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, ANO CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-13.

SALEM - UN IT 2 3/4 3-59 Amendment No.~

REACTOR COOLANT SYSTEM 3/4.4.9 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4. 9 The specific activity of the primary co'olant shall be l im.ited to:

a. Less than or equal to 1.0 µCi/gram DOSE EQUIVALENT I-131, and

b. Less than or equal to 100/t µCi/gram~§' 0

" f/J'i~

APPLICABILITY: MODES 1, 2, 3, 4 and 5.

ACTION:

MODES 1, 2 and 3*:

With the specific activity of the primary coolant ~ter ~

1.0 µCi/gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval or exceeding the limit line shown on Figure 3.4-1, be in at least HOT STANDBY with Ta ~~~a-S00°F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . v ~

With the specific activity of the primary coolant ~r tMa~

100/t µCi/gram, be in at least HOT STANDBY with Tav~ss thas> S00°F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . . @

With Tavg .il"****r *"/i I.

tifsoo°F.

SALEM - UNIT 2 3/4 4-23

-* REACTOR COOLANT SYSTEM ACTION: (Continued)

MODES 1, 2, 3, 4 and 5:

a. With the specific activity of the primary coolant greater than 1.0 µCi/gram DOSE EQUIVALENT I-131 or greater than 100./t µCi/gram, perform the sampling and analysis requirements of item 4a of Table 4.4-2 until the specific activ,it o ri a coolant is restored to within its limits.

1. Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded,

2. Fuel burnup by core region,

3. Clean-up flow history starting 48 heurs prior to the first sample in which the limit was exceeded,

4. History of de-gassing operations, if any, starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded, and 5.

SURVEILLANCE REQUIREMENTS 4.4.9 The specific activity of the primary coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-4.

SALEM - UNIT 2 3/4 4-24

RADIOACTIVE EFFLUENTS

~

LIMITING CONDITION FOR OPERATION J.11.1.2 The dase ar dase comraitment to a MEMBER OF THE PUBLIC from rad1oactfve materials 1n liquid effluents released, frcm each reactor unit, to UNRESTRICTED AREAS {see Ffgure 5.1-3) shall be limited:

a. During any calendar quarter ta less than ar equal to l.S mrems to the total bady and to less than ar equal ta ~ mrems to any organ, and

b. During any calendar year to less than or equal to 3 mrems to the* total body and ta less than or equal ta 10 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

a. With th* calculated dose fram

th* release af radioactive materials f n liquid effluents exceeding any of the above 11m1ts, ~ii Hau of a>- 2 tCJiien,ee=£yent=Reaact:~ prepare and sub*ft to the Camrtssion within 30 days, pursuant ta Spteiffcatian S.9.2, a Special Report that identifies the cause(s) far exceeding th* .11nrit(s) and defines the corrective actions that have bten taken ta reduce the releases and the proposed carrective actions to bt taken to assure that subsequent releases wfll be fn compliance with th* abov* limits.

b. The provfsi-ans at' Spte1ficat1an 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.ll.1.2 Cumulative dose contributions frcm liquid effluen~ shall be determined 1n accordance with the OOCM at least once per 31 days.

SALEi'! - UNIT 2 3/4 ll-5 No.~

Amendment

RADIOACTIVE EFFLUENTS LIQUID RAOWASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.t.l Th* lfqufd r1dw1st* tre1tm1nt syst111 shall be used to reduce the r1dfo1ctfve 1111ter11ls lfqufd wast1s prfor ta thefr discharge when the projected v*

c:unulatf doses du* to th* lfqufd effluent fraa each reactor to UNRESTRICTED AREAS (s** Ff gu,.. 5.1-3) exc19d 0.375 mrem to the tot~l body or 1.25 mrem to any org111 during any calendar quarter.

APPLICABILITY: At all tfmes.

ACTION:

1. Wftn th* r1dfo1ctfve lfqufd W&Ste befng discharged wftnout treatment and fn excess of th* above lfmftsan Heu ef 1 Lfe.,.se* Event ReH~

Pr"'9Plr9 and submit ta th* Caaafssfan wfthfn 30 daysJpu191uant to Sp.:ff1Cltfon S.9.21 1 Sp.:111 Report th1t includes th* following fnfarmatfon:

1. 'Expl1n1tfan of why lfqufd r1dw1st* w1s being d1sdt1rged without t1"91tmltrt, fdentf ffcatfon of any fnaperabl* 1qufpment or '.

subsystlllS, and th* reason fot the fnoperabf lfty.

z. Actfon(s) taken ta resto,.. the fnaperable 1qufpment to OPERABLE status, and

3. Sumlal":f descrf ptf on of actfan(s) taken ta pravent a recurrenc1.

b. Th* prov1sfons of Sp.:fffcatfon 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE R!QUIREMEMTS 4.11.1.3 Oases due ta lfqufd ,,leases shall be projected at least onca per 31 days f n accordanc* wftn th* 0004.

SAL£M

UNIT Z 3/4 11-0 ~endment ~o.~

RADIOACTIVE EFFLUENTS COSE

NOBLE* GASES LIMITING CONDITION FOR OPERATION 3.ll.2.2 Th* air dose due to noble gases released 1n gaseous effluents, from each reactor unit, frClll the s1te areas at and beyond the SITE BOUNDARY (see Figure S.l-3) shall be 11m1tld to th* tallowing:

a. During any calendar quarter: Less than or equal to S mrad for gaJT911a rad1at1an and 1ess.thtn ar equal to 10 ~rad for beta rad1at1on and,

b. During any calendar year: Less than or equal ta 10 mrad for ganma rad11t1on ~nd l*ss than ar equal ta 20 mrad for beta radiation.

APPLICABILITY: At all t1119s.

ACTION:

a. With the calculated a1r dose fronr radioactive noble 94ses in gaseous effluents exc1eding any of ~* abov. limits, GfJ£]1tu:..Of a Lf cen~

__,9-ivtnt P*daffi prepare and submit to the CClllll1ssion within 30 days, pursuant ta Specification S.9.2, a Special Report that ident1f1es the cause(s) for exceeding the limit(s) and defines th* corrective actions that have been taken ta reduca the release and th* proposed corrective actions ta be taken ta assure that subsequ*nt releases will be 1n c:cmp l1 anca w1 th the above 1i nrt ts. *

b. *Th* prov1s1ons of Spec1f1cat1ons 3.0.3 and 3.0.4 ar-e not applicable.

SURVEILLANCE REQUIREMENTS 4.ll.2.2 Cumulative dose contr1but1ons far the current calendar quarter and current calendar year shall b* determined 1n accordance with the OOCM at least once per 31 days.

SALE11

UNIT Z . 3/4 ll-12 Amendment Na. ~

RADIOACTIVE EFFLUENTS DOSE - IOOINE-131, TRITIUM, ANO RAOIONUCLIOES IN PARTICULATE FORM LIMITING CONDITION FOR OPERATION .

3.ll.2.3 The dose to a MEMBER* OF THE PUBLIC fran fodine-131, fran tritium, and fram all rad1onuc11des in particulate form with half-lives* greater than a days in gaseous effluents released, fran each reactor unit~ fran the site to areas at

.and beyond the SITE BOUNDARY (see Figure S.l-3} shall be limited ta th.e foll owing:

a. Curing any ca 1end1r quarter: Less than or equal ta 7. 5 mrems ta any organ and, *

b. Curing any ca 1endar year: Less than or equa 1 ta 15 mrems ta any organ.

APPLICABILITY: At al 1 times.

ACTION:

~t,r

a. With th* calculated~dose from the r.leue of _iod1ne-l3l, tritium, and radionuclides fn particulate farm with half-lives greater than a

days, 1n gaseous effluents exceeding any of the above 11mits,<fiL)~

~ a Lt C:eosew Event Ripiiffl prepare and submit ta the Comnrt ssi on wi tl'li n 30 days, pursuant ta Specification 6.9.2, a Special Report that identifies th* caus*(s} for exceeding the 11m1t and defines the corrective actions that hive been taken ta 1"9duc* the rel ease and the proposed carr~tive actions ta be taken ta assure that subsequent re 1eases wi 11 be 1n comp 1fan*ce with th* above l 1mi ts.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.ll.Z.3 Cumulative dose contributions for the current calendar quarter and current calendar year for 1od1ne-l3l, tritium, and radionuclfdes in particulate form with half-lives greatar than a days shall be determined fn accordance with the OOCM at least once per 31 days.

SALEM - UNIT Z Amendment N~. -~

RADIOACTIVE EFFLUENTS GASEOUS RAOWASn TREA'T1"ENT LIMITING CONDITION FOR OPERATION 3.11.2.4 Th* GASEOUS RADWASTE TREAT?i4EMT SYSTa4 and th* VEMTILIATION EXHAUST TREAT?i4EMT SYSTEM shall be used ta reduce rad1oact1ve"1111ter11ls fn gaseous waste prior to th*f r d1sdlarg* when th* projected gas*ous effluent a1r doses du* to gaseous effT uent re 1eues, fl"QI th* s1 t* ta 1.-.u at 111d beyond th* SIn BOUNDARY (s** F1gul"9 5.l*3)0 exca.d 0.525 lll"ld for gamma rad1at1on and 1.%5 mrad CV. for beta radiation in 1111 calendar qu1rt1r. The .VEHTILIATION EXHAUST TREAT?i4EMT SYSTEM shall b* used to reduce rad1a.c:t:iv* 1111t1rials tn gaseous wast* prior to their dtscharga when th* proj1c:t:ad das*s due ta gaseous 1fflu1nt rel11sts, fran i1ch reactor unit, fra11 the s1ta to al"9as at ~d beyond th* SITE BOUNDARY (see f'1gure 5.1*3) would ucHd' 1.875 Ill"* to any organ 1n lll'J calendar quarter

APPLICABILITY: At all times.

ACTION:

1. W1 th gas.ous wast* bet ng

di schargad without treat~and 1n excess of th~ 1bave 111111ts(7'1n 11111 or 1 t1e1ns11 Evtni Ripa~ prepare and sublll1t ta the Ccnmission w1thfn 30 days, pursuant to Specif1cat1on 5.9.2, 1 Special R*part that tncludts th* following 1nfor1111t1on:

1. ~planation ot why gas*ous ra~sta was be1ng discharged without tl"91Clllnt 1 1darti1f1cat1on at 1111 tnaptrablt equ1p1119nt or subsyst1111S, and th* reuon for th~ 1nap*rab111 ty ,

z. Act1on(s) taken ta restore th* tnop1r1ble equipmnt *~

OPERABU status, and * * *

3. SWllll.lry dtscr1pt1on of acttan(s) taken to prevent a recurrence.

b. Th* p~v1s1ons at Spec1f1cat1ons 3.0.4 art nat app11cablt.

2 6.0.3 Qr1d)

SURV!ILl.AHC! REQUIREM!MiS I 4.11.2.4 Oases dut to gas1aus releases fran th* site shalt b* p~jected at lta$t ance per 31 days 1n accardanca with the ODCM.

SALEM

UNIT 2 3/4 ll-l4 Mendment Na.~

RADIOACTIVE EFFLUENTS 3/4.11.3 SOLIO RADIOACTIVE WASTE LIMITING CONOITION FOR OPERATION

3.ll.3. The solid radwaste system shall be used in accordance with a PROCESS CONTROL PROGRAM to process wet radioacti.ve waste "to meet sh1pp1ng and burial ground requirements.

APPLICABILITY: At all times.

ACTION:

a. W1th the pMJvis.ions af the PROCESS CONTROL" PROGRAM not satisfied *.

suspend shipments of defectively pMJcessed or defectively packaged solid radioactive wastes from the site.

b. The provisions of Specifications applicable *

3~0.3 and 3.0.~ a.9.t.9~ not

SURVEILLANCE REQUIREMENTS 4.ll.3. The PROCESS CONTROL PROGRAM shall be used

of to~ the SOLIDIFICATION at least one representative test specimen from at~~very tenth batch of each type of 'fllet radioactive waste (e.g., filter sludges, spen~(f::)

.evaporator bottoms, boric acid solutions, and sodiwn sulfate solutions).

a. If any test specimen fails to verify SOLIDIFICATION, the SOLIOIFICATION of the batch under ~est shall be suspended until such time as additional test specimens can be obtained, alternative SOLIOIFICATION paramete~ can be d*termined in accordance with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION. SOLIDIFICATION of the batch may then be resumed using the alternative SOLIDIFCATION

parameters determined by the PROCESS CONTROL" PROGRAM.

b. If the.initial test specimen from a batch of waste fails to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall provide for the collection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least three consecutive .inithl test specimens demonstrate SOLIDIFICATION. The PROCESS CONTROL PROGRAM shall be modified as required. as provided in

- Specification 5.13, to assure SOLIDIFICATION of subsequent batches of waste.

Amendment .No. ~

SALEM - UNIT 2 3/4 11-17

RADIOACTIVE.EFFLUENTS 3/4.ll.4 TOTAL COSE LIMITING CONDITION FOR OPERATION 3.11.4 The annual (calendar year) dose or dose comarf tment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and radiation, frcm urna1wn fuel cycle sources shall b* limited to less than or equal to ZS mrems to the total body or any organ (except tht thyroid, which shall bt limited to less than or equal to 75 mrems).

APPLICABILITY: At all times

.ACT!ON:

a. With the calculated doses from th* release of radioactive materials in liquid or gas*ous effluents exceeding twice the 111111ts of Specif1cat1on 3.11.1.za, 3.11.1.Zb, 3.ll.2.2a, 3.11.2.2b, 3.11.Z.3a, or 3.11.2.lb, calculations should bt made including d1rect radiation contributions

from the reactor un1ts and fraa outsidt storage tanks to dttermine whtthtr th* linrfts of th1s S~tcificat1on havt betn exceeded. If such 1~ the case ({ii 1fiil cf 1 1Jtn11e Event Rego~ prepa,.. and subllli t to the Cannission within 30 days, pursuant to Specification 5.9.2, a Special ~eport that dtfints th* corrective action to be taken to reduce

.. subsequent 1"91 eases to prevent 1'9currenc. of uc1tdi ng the above 11m1 ts and tncludts the schtdult for achieving confol"'lftlnc1 with the above

l111its *.

This Specic:al Report, as dtfintd in 10 CFR Part 20.405c, shall include an analysis that 1stima~*s the rad1at1on exposure (dose) to a ME1'18ER OF TiiE PUBLIC fl"all uran1wn fuel cyclt sources, including all eff1utnt pathways and direct radiation, far the calendar year that includes th* release(s) cover.C by this report *. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of th* exposure levels or canc.ntrations. If

~estimated dose(s) excee<fs th* abovt limits, and if the release lY~condtion resulting in v1olat1on of 40 CFR Part 190 has not already be9n corrected, th* Special Report shall include a request for a variance in accordanc1 w1th th* ~ravis1ons of 40 CFR Part 190. Subm1ttal of the re~art 1s cons1d*~ a timely request, arid a var1anca 1s granted unt11 staff acti.an on th* request is ccm~l eta.

SALEM

UNIT 2 3/4 ll-18 Amendment No *. ~

3/4.12 RADIOLOGICAL ENV!RONMENTAL MONITOR!NG 3/4.12.l MONITORING PROGRAM LIMITING CONDITION FOR O~ERATIOH

3.12.l. The radiological environmental monitor1 ng program shall be conducted as specified 1n Table 3.12-l.

APPLICABILITY: At all times.

ACTION:

a. With the radiological environmental monitoring program not beini* _12

. c:onducted as spec1fi ed in Tab le 3.* 12-1, dJi' Ueu of a L1 eeftsee 6=eAJ::J

~ prepare and submit to the Conmission, in the Annual

~~~ic:al Environmental Operating Report required by Spec:1f1cation

~ ~~~.1~, a desc:ription of the reasons for not c:onduc:ting the program as l"equired and th~ plans for preventing a rec:urrence. *

b. With the level of radioac:tivity as th* result of plant effluents in an environmental sampling medium at a specified location exc:eeding the reporting levels of Table 3.12*2 when averaged over any calendar quarter,can 111u if 1 l1eensee Event: Report::;eprepare and submit to the Commission within 30 days, pursuant to Specific:ation 6.9.2, a Spec:ial Report that identifies the .c:ause(s) for exceeding the 11mit(s) and defines the corrective ac:ti ans to be taken to* reduc:e radi oac:t i ve effluents so that the potential annual dose ta a MEMBER OF THE PUBLIC is less than the calendar year limits of Spec:ifications 3.11.1.2, 3.11.2.2, and 3.11.2.3. When more than.one of the radionuc:lides in Table 3.12*2 are detec:ted 1n the sa1111211ng medium, this report shall be submitted if:

c:onc:entrat1on (1) concentration (2)

+ - - - - - - - - + ** *ll.0 reporting level (1) reporting level (2)

When radionuclides other than those in Table 3.12*2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a member of the public: is equal to or greater SALEM

UNIT 2 3/4 12-l Amendment No.~

r 3/4.12 RAOIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.l MONITORING PROGRAM LIMITING CONDl!!ON FOR OPERATION ACTION: (Can~. 'd) than the calendar year 11m1ts of Spec1f1ca~1ons 3.U.l.Z, 3.ll.2.Z, and 3.11.2.3. This report 1s not required 1f the measured level of rad1oact1v1ty.was not the result of plant tffluents; however, 1n such an 1v.nt, th* cand1tfon shalt be reported-and described in the Annual Rad1atog1eat Env1ron1111ntal Operating Report *

c. With milk or fresh ltafy v*getabte sa11q2t1s unavailable from one or *mare of th* sample locations required by Tablt 3.12-1,* identify locations far. obtaining replactmtnt samples and add them ta th* rad1olog1cal environmental monitoring program within 30 days. The spec1f1c locations from which samples were unavailable may then be deleted from th* man 1tori ng program.

h * .

<II lhu a:f a L1Cense1 Event Report ifti£ursuant ta Spec1f1cat1on 5.9.1.J.i, id*nt1fy th* cause of th* unava1tab111ty of s~lts and the new tocation(s) for obtaining ~tacement samples 1n th* next Senrtannuat Radioactive Effluent Release Report. Include in the report a rev1s~ f1gure(s) and table for th* ODCM reflecting the ~e'llf 1ocat1on(s). - ..

d. Tht prov1s1ons of Specif1cat1ons 3.0.3 and 3.0.4 are not applicable *.

SURVEILLANCE REQUIREMENTS 4.12.l Tht rad1olog1cal environmental rnan1tor1ng samples shalt be collected pursuant to Table 3.12-l fra11 tht locations specified 1n the OOCM and shall be analyztd Pl.ll"Suant ta th* requirements of Table 4.12*1.

SALEM - UNIT 2 3/4 12-2

TABLE l.12-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIAONHEHTAL SAMPLES c llR:parttng teve!$.-<..

z

-t N

Water Atrborne Partlculjte' Fish Hiik Food Products Anilysh (pCl/l) or Gises (pCl/a ) (pCt/K9 1 wet) (pCt/l) (pCt/Kg, wet)

~

H-l 2 x 104(~

Hn-54 l x tol 3

104 ~

fe-59 4 x 102 I *1 104 '

.Co-58 a x aol 3 x 104 Co-60 l x 102 I x 104

...... Zn-65 l x 102 2 x 104 N

I Q)

Zr-Nb-95 4 x 102 1-lll 2 0.9 3 I x 102 Cs-ll4 lO lO .I x lOl 60 1 x 101 Cs-ll7 50 *20 2 x 101 10 2 x 101 B.i-La-140 2 x 102 ' l x 102 .

{t( for drtnk tog w.iter UlllPles. This ts 40 CFR Part IU v1lue. :CF no ofr,'nlhi11{ Wo-fe.t f"'/twy Kt'$~, a. \14(ue o-F "3 x 10"' pCi (I ~ety loe K~eol.

J

TABLE 4.12-1 HAXIHUH VALUES FOR THE LOWER LIMITS Of DETECTIOH.(lLD) c

~

-i N

Water Airborne Particulate ftsh Jttlk food Products Sediment

Analysts (pCt/l)

or Gases (pCt/*l) (pCt/Kg, wet) (pCt/l) (pCt/Kg, wet) (pCt/Kg, dry) gross beta 4 1 x l0-2 H-J 200&0 Hn-54 15 130 fe-59 30 260 Co-58 60 15 130 1

N Zn-65 JO 260 OD Zr-f@-95 15 1-131 0 1 x 10-2 1 60 Cs-nit./ 15 5 x 10-2 130 15 60 150

);:>

3

~ Cs-131 18 6 x 10-2 150 18 80 180

~

ID Ba-La-140 15 15

JI

z 0

N

())

TABLE 4.12-l (Cont'd)

TABLE NOTATION a ~equired detection capabi11t1ts for thennaluminescent. dosimeters used for

!;7;~anmental 1111asurements are given 1n Regulatory Guide 4.13, Rev. l, July b The LLD ts daf1ne<i tn Table 4.11*1.

olr1'11 ~1'11j wa.fer pa..fl.~e:..( e.,yisfs, .~ Vt<lue o-F

nay he tA-~d.

1-t- D ~r Jr~n l{;llj ~fer <;am/i /.,,,., .TF /I"' ,,/n*n 141/lj M> fer f> fl, .,;ar e,o-sfs ti.. e U[)

I o-F ?'"" /1'7C1 1'.!;o f,,f, 'c an:._ Ir$'(.,

fY1ay be u~ecJ.

SALEM

UNIT 2 3/4 12-10 Amendment No. ~

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LANO USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2. A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal~ the nearest residence and the nearest garden* of greater than 50 m2 (500 ft ) producing broad leaf vegetation. (For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977. the land use census shall also identify within a distance of 5 km (3 miles) the locations in each of the 16 rneteorological sectors of all milk animals and all gardens of greater than 50 m2 producing broad leaf vegetation. ~

APPLICABILITY: At all times.

ACTION:

a. With a land use census identifying a location(s) that yields a .,.

calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, a lieu gf a bOjeeasee -g~

b.

>2-<Reilirb identify the new location{s) in the next Se'"iannual Radioactive Efflue~t Release Report, pursuant to Specification 6.9.l.~

With a land use census identifying a location(s) that yields a

(

y calculated dose or dose commitme11t (via) the sarne exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, add the new location(s) to the radiological environmental rmnitoring progra'" within 30 days. The sampling*location(s). excluding the control station location, having the lowest calculated dose or dose commitment(s) (via the sal11! exposure pathway) may be deleted from this rronitoring program after October 31 of the year in which this land use census was

/~

conducted.~ 1el Of a--tieeMee Eveet Repnct arial)Rlrsuant to SpecificaticllF.9 ** it, identify the new location(s) in the next

~ Semiannual Radioactive Effluent Release Report and also inclu~e in the report a revised figure(s) and table for the OOCM reflecting the new location (s).

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of t~ different direction sectors'with the highest predicted 0/Q in lieu* of the garden census;.

Specifications for broadleaf vegetation sampling in Table 3.12-l.4c shall be followed, including analysis of control samples.

f SALEH - UNIT 2 3/4 12-11 Amendment No.~

RACCOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS (Cont'd)

SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted during the growing season at least onc:e per 12 months usift9 that information that will provide the best 1"9su1ts, such as by a door-to-door survey, aerial survey, or by consulting local agr1culture author1ties. Th* results of the land use census shall be included 1n th* Annual Rad1olog1ca1 ~nv1ronmenta1 Operating Report pursuant ta Spec1f1cat1on 6.9.1~. *

(j)

SALEM - UNIT 2 3/~ 12-12 Am~ndment No.r

- - RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3. INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Pro9ram which has been approved by the Commission.

APPLICABILITY: At all times.

ACTION:

a. W1th analyses not being performed as required above, report the correct1ve actions taken to prevent a recurrence to the Ccmmfssfon fn the Annual Rad1olog1cal Environmental ~perat1ng Report pursuant to Spec1f1cat1on 6.9.l.~

b. The prov1s1ons of Spec1f1cat1ons 3.0.3 and 3.0.4. are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.3 A summary of the results obtained as part of the above required Interlaboratory CO!lll2ar1son Program and fn accordance wfth the OOC."' shall be fnclude<I fn the Annual Rad1olog1cal Environmental Operating Report pursuant to Spoclflcat1on 5.9.~,

SALEM - UNIT 2 . 3/4 12-13 Amendment No. W ~

POWER DISTRIBUTION LIMITS BASES

-~------------------------------------------------------------------------------

event. The penalties applied to F~H to account for Rod Bow (Figure 3*2-4) as a function of burnup are consistent with those described in Mr. John F. Stolz's (NRC) letter to T. M. Anderson (Westinghouse) dated April 5, 1979 and W8691 Rev. 1 (partial rod bow test data).*

When an FQmeasurement is taken, an allowance for both experimental error and manufacturing tolerance must be made. An allowance of 5% is appropriate for a full core map taken with the i~core detector flux mapping system and a 3i allowance is appropriate for manufacturing tolerance. When RCS flow rate and F~R are measured, no additional allowances are necessary prior to comparison with the limits of Figure 3.2-3. Measu~ement errors of 3.5% for RCS total flow rate and 4% for F~R have been allowed for in detennination of the design DNBR

value.

The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months periodic surveillance of indicated RCS flow is sufficient to detect

~ flow degradation which could lead to operation outside the acceptable

region of operation shown in Figure 3.2-3.

The radial peaking factor Fxy(z) is measured periodically to provide assurance that the hot channel factor, FQ(z), remains within its limit. The Fxy limit for RATED THERMAL POWER (F:f), as JcF\ided in the Radial Peaking Factor Limit Report per specification 6.9.l~was detennined from_ expected power control maneuvers over the full range of burnup conditions in the* core.

3/4.2.4 QUADRANT POWER T!LT RATIO

The quadrant power tilt ratio limit assures that the radial power distribution satisfies the design values used in the power capability analysis.

Radial power distribution measurements are made during startup testi~g and periodical-ly durin'g power operation *

SALEM - UNIT 2 B 3/4 2-5 Amendment No

19

REACTOR COOLANT SYSTEM BASES 3/4.4.9 SPECIFIC ACTIVITY

/

The limitations on the specific activity of the primary coolant ensure that the resulting 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months doses at the site boundary will not exceed an appropriately small fraction of Part 100 limits following a steam generator tube rupture accident in conjunct~on with an assumed steady state primary-to-secondary steam generator leakage rate of 1.0 GPM. The values for the limits on specific activity represent interim limits based upon a parametric evaluation by the NRC of typical site lo.cations. These values are conservative in that specific site parameters of the Salem site, such as site boundary location and meteorological conditions, were not considered in this evaluation. The NRC is finalizing site specific criteria which will be used as the basis for the reevaluation of the specific activity limits of this site. This reevaluation may result in higher limits.

The ACTION statement permitting POWER OPERATION to continue for limited time periods with the primary coolant 1 s specific activity greater than 1.0 µCi/gram OOSE EQUIVALENT I-31, but within the allowable limit showFI oFI figure 3.4-1, accommodates possib.le iodine spiking phenomenon i'lhich may occur 1

following changes in TMERMAL POWER. Operation with specific activ..:i-ty---l-eve exceeding 1.0 µCi/gram OOSE EQIJIVP.LENT I-131 but within the limits shown on \

/

Figure 3.4-1 must be restricted to no more than BOO hours per year (approxi-mately 10% of the 1;mit 1 s yearly operating time) since the activity levels '

allm*ted by Figure 3.4-1 increase the 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months thyroid dose at the site boundary by a factor of up to 20 following a postulated steam generator tube rupture.

The reporting of cumulative time 0*1er SOO hours in any a month consecutive period with greater than 1.0 µCi/gram DOSE EQUIVALENT I-131 will allow sufficient time for Commission evaluation of the circumstances prior to reaching the

-890 !lour 1i mit.

Reducing T v to less than S00°F prevents the release of activity should a steam generat8r9tube rupture since the saturation pressure of the primary coolant is below the lift pressure of the atmospheric steam relief valves.

The surveillance requirements provide adequate assurance that excessive specific activity levels in the primary coolant will be detected in suffi-cient time to take corrective action. Information obtained on iodine spiking will be used to a*ssess the parameters associated with spiking phenomena. A reduction in frequency of isotopic analyses following power changes may be permissible if justified by the data obtained.

SALEM - UNIT 2 B 3/4 4-6

ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY

6.1.1 The General Manager - Salem Operations shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 The Senior Nuclear Shift Supervisor or, during his absence from the Control Room, a designated individual shall be responsible for the Control Room command function. A management directive to this effect, signed by the Vice President and Chief Nuclear Officer, shall be reissued to all station personnel on an annual basis.

6.2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include positions for activities affecting the safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shall be established and defined from the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the Salem Updated Final Safety Analysis Report and updated in accordance with 10 CFR 50.7l(e).

b. The General Manager - Salem Operations shall be responsible for overall facility safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plants.

c. The Vice President and Chief Nuclear Officer shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plants to ensure nuclear safety.

d. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

6.2.2 FACILITY STAFF The facility organization shall be subject to the following:

a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

SALEM - UNIT 2 6-1 Amendment No.

ADMINISTRATIVE CONTROLS FACILITY STAFF (Continued) ~ 1~

~c.rov

b. At least one licensedJOperator shall be in the control room when fuel is in the reactor. In addition, at least one licensed Senior Reactor Operator shall be in thetontroltRoom area at all times.

~-r:F:~!£!, .

~

"'6... A ~ealU1

\C'eacte\C',

131<lysies tedu:iiciaA* shall be Ol'I site wheR fbtel is il'I the Aj/- CORE ALTERATIONS shall be observed and directly supervised by a licensed Senior Reactor Operator who has no other concurrent responsibilities during this operation.

A site Fire Brigade of at least 5 members shall be maintained onsite at all times*. The Fire Brigade shall not include 4 members of the minimum shift crew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency.

fl f. The amount of overtime worked by plant staff members performing safety-related functions must be limited in accordance with the NRC Policy Statement on working hours (Generic Letter No. 82-12).

The Operations Manager, Operating Engineer, Senior Nuclear Shift Supervisor~ and Nuclear Shift Supervisor$'shall each hold a senior reactor operator license. The Nuclear Control Operators shall hold reactor operator licenses.

SALEM - UNIT 2 Amendment No.

Figure 6.2-1 CORPORATE HEADQUARTERS AND OFF-SITE ORGANIZATION FOR MANAGEMENT AND TECHNICAL SUPPORT (Deleted) (

SALEM - UN IT 2 6-/[3 Amendment No.

FIGURE 6.2-2 FACILITY ORGANIZATION (Deleted) f

SALEM - UN IT 2 Amendment No.

--*~----- -

TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION SALEM UNIT 2

POSITION WITH UNIT 1 IN MODES 5 OR 6 OR DE-FUELED NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION MODES 1, 2, 3 & 4 MODES 5 & 6 SNSS la SRO none STA none NCO 1 EO/UO 2c Maintenance Electrician none Pa-J. fro, Tec-bfllciQn 1a., &L WITH UNIT 1 IN MODES 1, 2, 3 OR 4 POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION MODES 1, 2' 3 & 4 MODES 5 & 6 SNSS la la

SRO STA NCO EO/UO Maintenance Electrician eo.cJ. fro. Tec..htJici'aVI lb lb 2d 3

la I "'--

none none 1

1 none I q_

~/ Individual may fill the same position on Unit 2 Q/ Individual who fulfills the STA requirement may fill the same position on Unit 2. The STA, if a licensed SRO, may concurrently fill the SRO position on one unit; the other unit also reqµires a qualified SRO on shift.

~/ One of the two required individuals may fill the position on Unit 2, such that there are a total of three EO/U0 1 s for both unlts.

QI One of the three required individuals may fill the same position of Unit 2, such that there are a total of five EO/U0 s for both units .

1

.e../ Abf f/@"o/ec/ 1-F Jcp.f/, R?ac-/?it.5 ~r-R ofe--Gi:;o~

SALEM - UNIT 2 6-/F Amendment No. 33

TABLE 6.2-1 (Continued)

SNSS - Senior Nuclear Shift Supervisor with a Senior Reactor Operator License on both units.

SRO - Individual with a Senior Reactor Operator License on both units (normally, a Nuclear Shift Supervisor ).

NCO - Nuclear Control Operator with a Reactor Operator License on both units.

STA - ShiftrTechnical Advisor (if licensed as SRO, may be assigned duties as a Nuclear Shift Supervisor).

EO/UO- Equipment Operator or Utility Operator.

Except for the Senior Nuclear Shift Supervisor, the Shift Crew Composition may (

be one less than the minimum requirements of Table 6.2-1 for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate the unexpected absence of on-duty shift crew members provided that immediate action is taken to restore the Shift Crew Composition to within the minimum requirements of Table 6.2-1.

This provision does not permit any shift crew position to be. unmanned upon shift change due to an oncoming shift crewperson 1 s being late or absent.

During any absence of the .Senior Nuclear Shift Supervisor from the Control Room area while the unit is in any MODE, an individual with a valid SRO License shall be designated to assume the Control Room command function.

SALEM - UNIT 2 Amendment No. ~

ADMINISTRATIVE CONTROLS 6.2.3 SHIFT TECHNICAL ADVISOR 6.2.3.1 The Shift Technical Advisor shall serve in an advisory capacity to the Shift Supervisor on matters pertaining to the engineering aspects assuring safe operation of the unit.

6.2.3.2 The Shift Technical Advisor shall have a Bachelor's Degree or equivalent in a scientific or engineering discipline with specific training in plant design and response and analysis of the plant for transients and accidents.

6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, except for the Radiation Protection Engineer who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.

or f2a.J,'a..fleJn p,.." fec.f1on/cJ.emis ft-y #!wrver 6.4 TRAINING . .

6.4.1 A retraining and replacement training program for the facility staff shall be coordinated by each functional level manager (Department Head) at the facility and maintained under the direction of the Manager - Nuclear Training

~hall meet or exceed the requirements and recommendations of Section 5.5

~ of ANSI NlB. l-1971 and A1919endix A ef'VlO CFR Part 55. al"ld the suppl emel"ltal 11 11 requirements specified in Sections A aAd C of El"lelosure 1 of tl"ie Mal"eh 28, 1980 NRG lettel" to all lieel"lsees, al"ld sl"iall iAcl~de familial"ization wit~

-rel e¥ant industry opera.ti on al experience.

6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Manager - and shall meet or exceed the requirements of Section 27 of NFPA Code-1975, except for Fire Brigade training sessions which shall be held at least quarterly.

Pr~f7'cJr?)

SALEM - UN IT 2 6-tS 7 Amendment No. ~

ADMINISTRATIVE CONTROLS 6.5 REVIEW AND AUDIT

6.5.1 FUNCTION STATION OPERATIONS REVIEW COMMITTEE (SORG) 6.5.l.l The Station Operations Review Committee shall function to advise the General Manager - Salem Operations on operational matters related to nuclear safety.

COMPOSITION 6.5.1.2 The Station Operations Review Committee (SORG) shall be composed of:

5c= 'J:wSGRT To fl, s; I.~

Ch.airman: General Manager Salem Operations Member and Vice Chairman: ."..sst. General Manager SalC:HJ: Operatiens

.Member and Vice Ch.airman: Maintenanee Manager

.Mlmb<H and Vice Chairman: Operations Manager Member and Vice Chairman: Technical Manager Member: Operating Engineer Member: I & C Engineer Member: Senior Nuclear Shift SUfHn*visor Member: Technical Engineer Member: Maintenance Engineer Member: Radiation Protection Engin~

Member: Chemistry Engineer Member: Manager On Site Safety Review Group or his designee .

ALTERNATES SrE XAJSE~I To ~. 5". I. 3 6.5.1.3 All alternate members shall be appointed in writing by the SORG Chairman.

a. Vice Chairmen shall be members of Station management.

b. Ne mere than two alternates to members sh.all participate as voting members in SORG activities at any one meeting.

e. hlternate appointees will only represent their respeeti~e department.

d. f,lternates for members will not make up part of the voting quorum when the members the alternate represents is also present.

MEETING FREQUENCY 6.5.1.4 The SORG shall meet at least once per calendar month and as convened by the SORG Chairman or his designated alternate.

QUORUM 6.5.1.5 The minimum quorum of the SORG necessary for the performance of the SORG responsibility and authority provisions of these technical specifications shall consist of the Chairman or his designated alternate and five members including alternates.

£ft: -:!",V5i=RI 10 ~. 5. /. b SALEM - UNIT 2 6-~ ~ Amendment No. 33

INSERT TO SECTION 6.5.1.2 Chairman: General Manager - Salem Operations Member and Vice Chairman: Maintenance Manager Member and Vice Chairman: Operations Manager Member and Vice Chairman: Technical Manager Member: Radiation Protection/Chemistry Manager Member: Radiation Protection Engineer Member: Chemistry Engineer Member: Maintenance Engineers Member: Operating Engineers Member: Technical Engineers (Group Heads)

Member: Onsite Safety Review Engineer INSERT TO SECTION 6.5.1.3 6.5.1.3 Alternates:

a. Alternates shall be appointed by the SORC Chairman in writing.

b. Only designated Vice Chairmen may act as Chairman of a SORC meeting in the absence of the General Manager -

Salem Operations.

c. The Senior Nuclear Shift Supervisor (SNSS) may act as an alternate for the Operations Manager or an Operating Engineer. The SNSS may also act as an alternate when the Operations Manager is acting as Chairman.

INSERT TO SECTION 6.5.1.5

a. No more than two members or one member and one alternate from any individual department will make up part of the voting quorum.

b. If the Chairman for a meeting is a Vice Chairman, then up to two additional members (or one member and one alternate) may be part of the voting quorum.

ADMINISTRATIVE CONTROLS RESPONSIBILITIES 6.5.1.6 The Station Operations Review Committee shall be responsible for:

a. Review of: (1) Station Administrative Procedures and changes thereto and (2) Newly created procedures or changes to existing procedures fei111.ire ~ IOC.FRS'CJ.':)<( t at

as described in Section Sa..f~dy evolu~fiol'J 6.5.3.2.d.

b. Review of all proposed tests and experiments that affect nuclear safety.

c. Review of all proposed changes to Appendix "A" Technical Specifications.

d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.

e. Review of the safety evaluations that have been completed under the provisions of 10CFR50.59.

J::µ;ficdion <:>r review QF vf nvestigation of all violations of the Technical Specifications including the preparation and forwarding ef reports covering evaluation and recommendations to prevent recurrence.t~

.President and Chief Nuelear Offieer and the General Manager Nuclear Safety Review.

g. Review of all REPORTABLE EVENTS.

h. Review of facility operations to detect potential nuclear safety hazards.

deierMi11ec/ ~y i. Performance of special reviews, investigations or analyses and

-Hie ~oRL. reports thereon as~requssted by the General Manager Salem Operations or General Manager Nuclear Safety Review. c a.n~,;-5

+i..f!reto.

j. Review of the Facility Security Plan and implementing procedures and submittal of recommended changes to the General Manager Nuclear Safety Review, dQn~e(> fh.er-efo

+/..a.t ret:11A.r're Cl k. Review of the Facility Emergency Plan and implementing procedures SQ-fu 7 ,__~~-aa~:n~~d~~~~~~~~~~~~~=(!~~~~~~~~~~~~~7!:~~~~'7:=:;~~

(OCFR.~e>.6Cfu 1 N 1 61 *n\/G V'2 cc fr:>'fenfi4/ decre4 (;e i'11 +lie f?Vt>>{uo.fiof\ ef:fed1'1f(!t!lt?t;'i oF +/.."" ?f4,.,, f<'r ftJ.C.i:~S0.5"'/ftt)

1. Review of the Fire Protection Program and implementing proce ures

'------::a:::n::dr.1.submittal of reeoH1H1ended changes to the General Manager Nuclear Safety Review.

m. Review of all unplanned on-site releases of radioactivity to the environs including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence. and the forwarding of these reports to the Vice Presid@ut and Chief Nuclear Officer and the General fiauager - Nuclear Safety Rcvieu.

SALEM - UNIT 2 6-t1 Amendment No.

ADMINISTRATIVE CONTROLS RESPONSIBILITIES (continued)

n. Review of changes to the PROCESS CONTROL MANUAL and the OFF-SITE DOSE CALCULATION MANUAL.

SORG REVIEW PROCESS I

6.5.1.7 A technical review and control system utilizing qualified reviewers shall function to perform the periodic or routine review of procedures and changes thereto. Details of this technical review process are provided in Section 6.5.3.

AUTHORITY 6.5.1.8 The Station Operations Review Committee shall:

Gal..-e.,,.l-1 YI{;>

Proviol-e a. ~to the General Manager - Salem Operation~~ritten approval f eCt>nlfll~Q. f;o115 or disapproval of items considered under 6.5.1.6. (a) t:hrottgh (e) above.

b. Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Vice President and Chief Nuclear Officer and the General Manager - Nuclear Safety Review of disagreement between the SORG and the General Manager -

Salem Operations; however, the General Manager - Salem Operations shall hav~esponsibility for resolution of such disagreements pursuant to 6.1.1 above.

RECORDS '1nl0 R.EPORl5 6.5.1.9 The Station Operations Review Committee shall maintain written minutes of each meeting and copies shall be provided to the Vice President and Chief Nuclear Officer, the General Manager - Nuclear Safety~ and the anager - Off Site Review. l~Q:--~/.*~J~A-:--~~~~~

t..1q 'T( n-S$Uf"tl11Ce o,,11c(

6. 5. 2 NUCLEAR SAFETY REVIEW ll'f\)t:J AllDIT FUNCTION 6.5.2.1 The Nuclear Safety Review Department (NSR) shall function to provide the independent safety review program and audit or' designated activities.

0MPOSITION Ser: .ItJSER.T I t"o SecT/(nJ ~- 5: 'J. ~

.6.5.2.2 NSR shall consist of the General Manager Nttclear Safety Review, the Manager On Site Safety Revieu Croup (SRC), who is supported by at least four dedieated, full bimo engineers located on-site, and the Manager Off-Site Review Croup (OSR) who is supported by at least four decliea:ted, full time engineers located off site.* The OSR staff shall po.eisess experience and compebence in bhe general areas lisbed in ~ecbion 6.5.2. 11. The General Manager and Managers shall determine when additional technical experts should assist in reviews of eomplex problems.

w Since the Nuclear Department is located on nrtificial Island site, the terms "on site" and "off site" convey the distinetion between inside and outside the station fence, respectively.

SALEM - UNIT 2 6-f (0 Amendment No.

INSERT 1 TO SECTION 6.5.2 COMPOSITION 6.5.2.2 The Nuclear Safety Department, under the cognizance of the General Manager - Quality Assurance and Nuclear Safety, shall consist of the Manager - Nuclear Safety, the Offsite Safety Review staff (OSR) and the Onsite Safety Review Group (SRG) . The OSR staff and the SRG each consist of at least four dedicated, full-time engineers.

The Manager - Nuclear Safety and the Offsite Safety Review staff shall meet or exceed the qualifications described in Section 4.7 of ANS 3.1 - 1981 and shall be guided by the provisions for independent review described in Section 4.3 of ANSI N18.7 - 1976 (ANS 3. 2) .

The Offsite Safety Review staff shall generally possess experience and competence in the areas listed in Section 6.5.2.4.1. A system of qualified reviewers from other technical organizations may be used to augment OSR staff expertise in the disciplines of Section 6.5.2.4.1, where appropriate. Such qualified reviewers shall meet the same qualification requirements as the Offsite Safety Review Staff, and shall not have been involved with performance of the original work.

The Onsite Safety Review Group staff shall meet or exceed the qualifications described in Section 4.4 of ANS 3.1 - 1981.

ADMINISTRATIVE CONTROLS (continued)

NSR shall u *it~e a system of qualified reviewers from other organizations to~t its expertise in the disciplin o Such qualified reviewerS---sb.!11 meet the same qual* *cation requirements as the NSR staff, and will not have~volved

performance of the original work.

The Manager ew and Staff shall mee exceed the qualifications des in Section 4.7 of ANS 3.1(198 by the prov*

ns for independent review described in Section Nl8.7 6) (ANS 3.2). The Manager - On Site Review and staff will the qualifications described in Section 4.4 of ANS 3.1 (1981).

CONSULTANTS ar ~ dv fee.. 11.-ced t!!yper-1-s 6.5.2.3 Consultants hall be utilized as determined ey the General Mana-ge'l'."" -

Nuclear Safety Review to provide expert advice to the NSR. l,y -f-ht' N<,u: lr!?cr -;;4. Fefy*

( ~fW ii.TY L

~FFiSIT~REVIEW OefOa.r+,.,~,-if* -/.:> -!-~ e e l<'fe'I f nee. e~~e; ty.

6fteY:P (o,;R)

~ ~~The Gff ~ite Reviiaw Gro11p /osR.6f"~unction to provide independent

~review and audit of designated activities in the areas of:

a. Nuclear Power Plant Operations

b. Nuclear Engineering

c. Chemistry and Radiochemistry

d. Metallurgy

e. Instrumentation and Control

f. Radiological Safety

g. Mechanical Engineering

h. Electrical Engineering

i. Quality Assurance

j. Nondestructive Testing

k. Emergency Preparedness Th OSR i;;hall also function to Xamine plant operating characteristics, NRG issuanc@s, industry advisories, Licensee Event Reports, and other sources whieh may indicate areas for improving plant safety.

SALEM - UNIT 2 6-Ya t( Amendment No.

ADMINISTRATIVE CONTROLS REVIEW 6.5.2.4.l

}..

~

The OSR shall review:

..,..~a , t.

a.--f/.>afetyv~valuations ~

...,l1 C"uChanges to procedures, equipment, or systemsjand yTests or experiments completed under the provisions of Seetion

~ to verify that such actions did not constitute an unreviewed safety question; _/_

,antx/ -res

..L * .L r~ e> I ~per1mt?/lf3

b. Proposed changes to procedures, equipment, or systems, hat involve an unreviewed safety question as defined in Scetion~

c. Proposed tests or experiments that invelve an tlnreviewed safety quest:ion as defined in i6ceti:bt-r~.

{!.~. Proposed changes to Technical Specifications or to the Operating License; o/ft. Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance;

£f. Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety; If,* All REPORTABLE EVENTS; All recognized indications of an t:Ynanticipated deficiency in some aspect of design or operation of safety relatea structures, systems or componentso'" +/,r.d cou/J a.f:F.,,c.f nue./'t!ar sa.Tefy/

h/. Reports and meeting minutes of the Station Operations Review Committee.

AUDITS

'g

~

6.5.2.0' Audits of facility activities that are re~uired ts be performed under the cogni~e ofi&SR, Bore listed "Below: T'1ese aud,'fs ~/.,"/( encoMp~s:s:

+he ~SR~ qff}

a. The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.

b. The performance, training, and qualifications of the entire facility staff at least once per 12 months.

c. The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems, or method of operation that affect nuclear safety at least once per 6 months.

d. The performance of activities required by the Operational Quality Assurance Program to meet the Criteria of Appendixt'.tB~OCFRSO, at least once per 24 months.

SALEM - UNIT 2 6-'1:"6- /~ Amendment No.

ADMINISTRATIVE CONTROLS AUDITS (continued)

e.

f.

The Facility Emergency Plan and implementing procedures at least once per 12 months.

The Facility Security Plan and implementing procedures at least once per 12 months.

g. Any other area of facility operation considered appropriate by the General Manager - Nuclear Safety Rev:;i,ew or the Vice President and Chief Nuclear Officer.

h. The Facility Fire Protection Program and implementing procedures at least once per 24 months.

i. ~aepenaent fire protection and loss prevention program il"1p/~r>?'/lf.e.f/on Hi:speetion and auait shall be perfermecl at least once per 12 months

.J nJc utilizing either~ualified offsite licenseet or an outside

'" eru qllffire protection~ -Fo-r~ prof@c., 1011 en ~nee (j~

a)" ~ inspection and audit ef the fire protection and los~

IJrogram shall be performed by a ~ualified outside.,.fire onsultant t least once per 36 months. <J!i?eenot(I"!) s ~11 h<?

q+;!r*-recf The radiological environmental monitoring program and the results thereof at least once per 12 months.

rf/"-f_ 1AJSEi:'F !

The above audits shall be conducted by the Nuclear Quality Assurance Department or an independent consultaE:=-as@='~uired. Audit ~ f }tlM a.11/

reeofflfflendations shall be reviewed by~ _ea~~ sfa.F-/!;) F ~ ""' I a.ucf; f

~_ :f 4Nf./5'2T a ref'<'r-1-s

~ ON@ITE SAFETY REVIEW GROUP (~~G2 6.5.2.5.I The On-Site Safety Review Group (SRG) shall function to provide: the review of plant design and operating experience for potential opportunities to improve plant safety; the evaluation of plant operations and maintenance activities; and advice to management on the overall quality and safety of plant operations.

The SRG shall make recommendations for revised procedures, equipment modifications, or other means of improving plant safety to appropriate station/ corporate management.

RESPONSIBILITIES

~

6.5.2.5.) The SRG shall be responsible for:

a. Review of selected plant operating characteristics, NRC issuances, industry advisories, and other appropriate sources of plant design and operating experience information that may indicate areas for improving plant safety.

b. Review of selected facility features, equipment, and systems.

SALEM - UNIT 2 6 -l'fl I 3 Amendment No.

INSERT 2 TO SECTION 6.5.2 RECORDS AND REPORTS 6.5.2.4.4 Records of OSR activities shall be maintained.

Reports of reviews and audits shall be prepared and distributed as indicated below:

a. The results of reviews performed pursuant to Section 6.5.2.4.2 shall be reported to the Vice President and Chief Nuclear Officer at least monthly.

b. Audit reports prepared pursuant to Section 6.5.2.4.3 shall be forwarded by the auditing organization to the Vice President and Chief Nuclear Officer and to the management positions responsible for the areas audited (1) within 30 days after completion of the audit for those audits conducted by the Quality Assurance Department, and (2) within 60 days after completion of the audit for those audits conducted by an independent consultant.

ADMINISTRATIVE CONTROLS RESPONSIBILITIES (continued)

c. Review of selected procedures and plant activities including maintenance, modification, operational problems, and operational analysis.

d. Surveillance of selected plant operations and maintenance activities to provide independent verification* that they are performed correctly and that human errors are reduced to as low as reasonably achievable.

~AUTHORIT~,,;t.ec /r:>r;,r ~,,,.:f.<?fy PeP4*-l-l'H~""f_/

6.5.2.6 NSR. sh~ report to and advise the Vice President and Chief Nuclear Officer on those areas of responsibility specified in Sections 6.5.2.4 and 6.5.2.5.

6.5.2.7 Reeords of NSR aetivities shall be prepared and maintained. Reports of reviews and audits shall be distributed as follows:

a, Reports of reviews encompassed by Section 6. 5. 2. 4 .1 above, shall be, prepE!red, approved and forwarded to the Viee President and Ghief-Nuelear Offieer, with.in 14 days following completion of t:h1 *nwiew,

b. t.udit reports encompassed by Section 6.5.2.4.2 above, shall be forwarded to the Vice President and Chief Nuelear Offieer and to the management positions responsible for the areas audited within 30 days after eompletion of the audit.

6.5.3 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.3.1 Programs required by Technical Specification 6.8 and other procedures which affect nuclear safety as determined by the General Manager - Salem Operations, other than editorial or typographical changes shall be reviewed as follows:

PROCEDURE RELATED DOCUMENTS 6.5.3.2 Procedures, Program and changes thereto shall be reviewed as follows:

a. Each newly created procedure, program or change thereto shall be independently rev.iewed by an individual knowledgeable in the subject area other than the individual who prepared the procedure, program or procedure change, but who may be from the same organization as the individual/group which prepared the procedure or procedure change. Procedures other than Station Administrative procedures will be approved by the appropriate Station Department Manager or by the Assistant General Manager - Salem Operations. Each Station Department Manager shall be responsible for a predesignated class of procedures. The General Manager - Salem Operations shall approve Station Administrative Procedures, Security Plan implementing procedures and Emergency Plan implementing procedures.

Not responsible for sign-off function SALEM - UNIT 2 6-1;1 IC( Amendment No.

_j

ADMINISTRATIVE CONTROLS PROCEDURE RELATED DOCUMENTS (continued)

b. On-the-spot changes to procedures which clearly do not change the intent of the approved procedures shall be approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator License. Revisions to procedures which may involve a change in intent of the approved procedures, shall be reviewed in accordance with Section 6.5.3.2.a above.

c. Individuals responsible for reviews performed in accordance with item 6.5.3.2a above shall be approved by the SORG Chairman and designated as Station Qualified Reviewers. A system of Station Qualified Reviewers, each of whom shall possess qualifications that meet or exceed the requirements of Section 4.4 of ANSI Nl8.l - 1971, shall be maintained by the SORG Chairman. Each review shall include a written determination of whether or not additional cross-disciplinary review is necessary. If deemed necessary, such review shall be performed by the appropriate designated review personnel.

d. dete mines that the documents involved re111 Ire 'lo te>CFR pr;.n ee>R-t;-a:HT-s-3:-E!:R:l:-'8::-i!HrC--s-a:re~.......gc-s-:31tt<e-s-, the documents shall be forwarded

~a. Fe of...; <e<1t1.f4-t1.-fion NSR for an independent review to determine whether or not an unreviewed safety question is involved, Pursuant to 10CFRS0.59, NRG approval of items involving unreviewed safety questions or Technical Specification changes shall be obtained prior to implementation.

NON-PROCEDURE RELATED DOCUMENTS 6.5.3.3 Tests or experiments, changes to Technical Specifications, and changes to equipment or systems shall be forwarded for SORG review and also to N5R for an independent review to determine whether or not an unreviewed safety question is invo ve . e results of reviews will be provided to SORG.

Recommendations for approval are made by SORG to the General Manager - Salem Operations. Pursuant to 10CFRS0.59, NRG approval of items involving unreviewed safety questions or requiring Technical Specification changes shall be obtained prior to implementation.

RECORDS /lflllJ REFORTS 6.5.3.4 Written records of reviews performed in accordance with i~6.5.3.2a above, including recommendations for approval or disapproval, shall be maintained. Copies shall be provided to the General Manager - Salem Operations, SORG,~ and/or NRG as necessary when their reviews are required.

(}l,09R -;;-fo..@

6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a. The Commission shall be notified and/or a report submitted pursuant to the requirements of Section 50.73 to 10CFR Part 50, and

b. Each REPORTABLE EVENT shall be reviewed by the SORG and the resultant Licensee Event Report submitted to NBR-~nd the Vice President and Chief Nuclear Officer. @-e o~ R <;-la..!+/-:)

SALEM - UNIT 2 6-~ lS- Amendment No.

ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a. The unit shall be placed in at least HOT STANDBY within one hour.

b. The NRG Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Vice President and Chief Nuclear Officer and General Manager - Nuclear Safety Review shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the SORG. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

d. The Safety Limit Violation Report shall be submitted to the Commission, the General Manager - Nuclear Safety Review and the Vice President and Chief Nuclear Officer within 14 days of the violation .

SALEM - UNIT 2 Amendment No.

ADMINISTRATIVE CONTROLS 6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained

covering the activities referenced below:

a.

b.

The applicable procedures recommended in Appendix 11 A11 of Regulatory Guide 1.33, Revision 2, February 1978.

Refueling operations.

c. Surveillance and test activities of safety related equipment.

d. Security Plan implementation.

e. Emergency Plan implementation.

f. Fire Protection Program implementation.

g. PROCESS CONTROL PROGRAM implementation.

h. OFFSITE DOSE CALCULATION MANUAL implementation.

i. Quality Assurance Program for effluent and environmental monitoring.

6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed and approved in accordance with Specification 6.5.1.6 or 6.5.3, as appropriate, prior to implementation and reviewed periodically as set forth in administrative procedures .

6.8.3 a.

b.

On-the-spot changes to procedures of 6.8.l above may be made provided:

The intent of the original procedure is not altered.

The change is approved by two members of the plant management staff, at least one of whom.holds a Senior Reactor Operator 1 s License on i the unit affected.

c. The change is documented and receives the same level of review and approval as the original procedure under Specification 6.5.3.2a within 14 days of implementation.

SALEM - UNIT 2 6-!S t7 Amendment No. 33

ADMINISTRATIVE CONTROLS 6.8.4 The following programs shall be maintained:

a. Primary Coolant Sources Outside Containment

A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident, to as low as practical levels. The systems include (recirculation spray, safety injection, chemical and volume control, gas stripper, recombiners, ... ). The program shall include the following:

(i) Preventative maintenance and periodic visual inspection requirements, and (ii) Integrated leak test requirements for each system at refueling cycle intervals or less.

b. In-Plant Radiation Monitoring A program which will ensure the capability to accurately determine the airborne iodine concentration in areas under accident conditions. This program shall include the following:

(i) Training of personnel, (ii) Procedures for monitoring, and (iii) Provisions for maintenance of sampling and analyses equipment.

c. Secondary Water Chemistry A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation. This program shall include:

(i) Identification of a sampling schedule for the critical variables and the control points for these variables, (ii) Identification of the procedures used to measure the values of the critical variables, (iii) Identification of process sampling points, including monitoring at the discharge of the condensate pumps for evidence of condenser in-leakage.

(iv) Procedures for the recording and management of data,

{v) Procedures defining corrective actions for off-control-point chemistry conditions, (vi) A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.

SALEM - UNIT 2 Amendment No. 28

ADMINISTRATIVE CONTROLS

d. Backup Method for Determining Subcooling Margin A program which will ensure the capability to accurately monitor the Reactor Coolant System Subcooling Margin. This program shall include the fo 11 owing:

(i) Training of personnel, and (ii) Procedures for monitoring

e. Postaccident Sampling A program* which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions. The program shall include the following:

(i) Training of personnel (ii) Procedures for sampling and analysis, (iii) Provisions for maintenance of sampling and analysis equipment.

It is acceptable if the licensee maintains details of the program in plant operation manuals.

SALEM - UNIT 2 6-1:'4-a t1 Amendment No. 42

ADMINISTRATIVE CONTROLS 6.9 REPORTING REQUIREMENTS ROUTINE REPOR~s@o REPORTABLE OCCURRENCE~

6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the

~Admini7trator~Ef[tAe RegieAal Office ef ~~ect1~A aAa ~Aforceme~unless otherwise note . ~ , ~I* .*

1 e31ony STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months*following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

ANNUAL REPORTs*~

6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall b~ submitted prior to March 1 of 'each

~: ::::::~ ::::~!a~::!'.}! s~amitteEI prier to Marc~ 1 ef t~--yeaj} e

~~A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station .

SALEM - UNIT 2. 6-li ?.JJ

ADMINISTRATIVE CONTROLS 6.9.1.5 Reports required on an annual basis shall include:

a. A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their as~iated man rem exposure according to work and job functionsf[!_ e.g., reactor operations and.

surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling.

The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dos~ received from external sources shall be assigned to specific major work functions.

b. The complete results of steam generator tube inservice inspections performed during the report period (reference Specification 4.4.5.5.bf) ~EE Xl./S£12T~

MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555 with a copy to the R-egieF1al ~-;:..

Admi ni stratorj \f tt:1e Regi 0F1al Qffi ee-, no 1ater than the 15th of each month ~

following the calendar month covered by the report. .

REPORTABLE OCCURRENCES-6.9.1.7 The REPQRTABLE OCCURRENCES of Speeifieatiofls 6.9.1.8 aRd 6.9.1.9-below, iAelYdiRg eorreetive aetioRs aRd measures to preveRt reeYrreRce, shall be reported to the NRC. SupplemeRtal reports may be reqYired to fylly describe

fiAal resolutioR of occurreRce. IR case of corrected or supplemeRtal reports, a liceRsee event report shall be completed aAd refereRce shall be made to tA-e-origiRal report date.

PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP 6.9.1.8 TRe ty13es of eveRts listed below shall be reported wi-tR-H-1 24 hoYrs by tele13h0Re aAd eoAfirme~ by telegraph, mailgram, or faesimile traRsmissioR to the AdmiAistrator of the Regioflal Office, or his aesigflate FIO later thafl the first workiRg day followiRg the eveRt, with a writteR followup report withiR 14 days. The writteA followup report sh~ll iReluae, as a miflim~m, a completes copy of a liceRsee eveRt report form. lAformatioR 13roviaea OFI the lieeRsee eveAt report form shall be su13plemeF1tea, as F1eeaea, by aaaitieflal F1arrative

material te provide complete explaRatioR of the circumstaRces surroYRdiAg the f ~This tabulation supplements the requirements of section 20.407 of 10 CFR Part 20.

SALEM - UNIT 2 6-16 ?.-/ Amendment No. 28

INSERT TO SECTION 6.9.1.5

c. The results of any specific activity analyses in which the primary coolant exceeded the limits of Specification 3.4.8. The following information shall be included: (1) Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while the limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than the limit. Each result should include date and time of sampling and the radioiodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodirie limit.

ADMINISTRATIVE CONTROLS PROMPT NOTIFICATION WITH WRITTEN FOLLOW-UP (Continued)

a. Failure of the reactor protection system or other systems subject limiting safety system settings to initiate the required protecti e function by the time a monitored parameter reaches the setpoint specified as the limiting safety system setting in the technic 1 specifications or failure to complete the required protectiv function.

b. peration of the unit or affected systems when any param ter o eration subject to a limiting condition for operatic con ervative than the least conservative aspect of th limiting cond"tion for operation established in the technical specifications.

c. Abnorma degradation discovered in fuel cladding pressure oundary, or primary containment.

d. Reactivity omalies involving disagreement th the predicted value of reactivity balance under steady state co ditions during power operation grea r than or equal to 1% del k/k; a calculated reactivity balan e indicating a SHUTDOWN ARGIN less conservative than specified in he technical specif' ations; short-term reactivity increase that correspond o a reactor period of less than 5 seconds or, i subcritical, unplanned reactivity insertion of more than 0.5% delt k/k; or oc urrence of any unplanned criticality.

e. Failure or malfunction of e r more components which prevents or could prevent, by itself, tH fulfillment of the functional requirements of system(s) e to cope with accidents analyzed in the SAR.

f. Personnel error or pro dural ina quacy which prevents or could prevent, by itself, t e f ul f i 11 ment of the' fun ct i ona l requirements of systems required o cope with ace ents analyzed in the SAR.

g. Conditions arisi from natural or man- de events that, as a direct result of the e ent require unit shutdown operation of safety systems, or o er protective measures requ ed by technical specificatio s.

h. Errors di covered in the transient or accident nalyses or in the methods sed for such analyses as described in t safety analysis report r in the bases for ihe technical specifica ions that have or coul ave permitted reactor operation in a manner ess conservative tha assumed in the analyses.

i. B rformance of structures, systems, or components that quires remedial action or corrective measures to prevent operati in a manner less conservative than assumed in the accident anal es in the safety analysis report or technical specifications bases, or discovery during unit life of conditions not specifically con 'dered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence* or development of an unsafe condition.

f./

~,/

. **/

SALEM - UN IT 2/ ~-=

Amendment No.

j.

effluents 3.11.1.1 or 3.11.2.1.

k. the l"

s in Specification 1.4 or 3.11.2.6 for the aaioactive materials in the liste ks. The written fo -up report shall include a schedule and a desc

ion of activities planned and/or taken to reduce the contents to *n the specified limits.

SALEM - UNIT 2 6-1:-7-a- Ql-] Amendment No.

The types of events listed below shall be the subject of written reports the U.S. Nuclear Regulatory Commission, Document Control Des ,

Washington, D.C. 20555, with a copy to the Regional Administrator of Regional Of

e within thirty days of occurrence of the event. The itten report shall i lude, as a minimum, a completed copy of a license event report form. In mation provided on the licensee event report t rm shall be supplemented, as n ded, by additional narrative material to ovide complete explanation of the c cumstances surrounding the event.

a. Reactor protec *on system or engineered safet feature instrument settings which a found to be less conserv ive than those established by the echnical specificatio but which do not prevent the fulfillment oft functional requir ents of affected systems.

b. Conditions leading aegraded mode permitted by a limiting condition plant shutdown required by a limiting condition c.

procedural controls which redundancy provided in r safety feature systems

d. Abnormal degradati of systems other than hose specified in 6.9.1.8.c above signed to contain radioact e material resulting from the fissi process.

e. of 1) more than 1 cu *e of radioactive material *n liquid effluents, 2) more than 150 curie of noble gas in gase us effluents. The report of an unplanned offsi release of radio ctive material shall include the following informa A description of the event and equipment involved.

Cause(s) for the unplanned release.

3. Actions taken to prevent recurrence.

4. Consequences of the unplanned release .

SALEM - UN IT 2 Amendment No.

ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL*ENVIRONMENTAL OPERATING REPORT*

~ Routine Radiological Environmental Operating Reports covering the

operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.

The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies with operational controls (as appropriate), and with previous environmental surveillance *reports, and an assessment of the observed impacts of the plant operation on the environment.

The reports shall also include the results of land use censuses required by Specification 3.12.2. The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all measurements taken during the period pursuant to the Table and Figures in the environmental radiation section of the ODCM; as well as summarized and tabulated results of locations specified in these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.

The missing data shall be submitted as soon as possible in __~_~upplementary report. CME? cove ro'nd >arnp 1't1p loc.a.f-lo115 /Jectr e s::fr£* [:3ouN0/l/2 j/ qnc/ a...

. I °CDY/ol a>v<?'iil'J fhe <3/'@ ef1's_f...l'I+ /oe.a.f-)'Oy!Sj cd)

The reports sha 1 a so include he following: a summary description of the radiological environmental moni oring program; at least two legible maps,,~

.5>-~~i§:fEi=JEl:i§!::amJS:HijJ§:!~~~~keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program, required by Specification 3.12.1; and discussion of all analyses in which the LLD required by Table 4.12-1 was not achievable.

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT*

(i"r-----...

'---" 6.9.1.lr Routine Radioactive Effluent Release Reports covering the operation of the unit during the previous six months of operation shall be submitted within 60 days after January 1 and July 1 of each year.

The Radio.active Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21. "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materi~s in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plar(t.i9 Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

SALEM - UNIT 2 Amendment No.

ADMINISTRATIVE CONTROLS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (continued)

The Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured),

or in the form of joint fre~ncy distributions of wind speed, wind direction, and atmospheric stability.*~his same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive -liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 5.1-3) during the report period.

All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency.and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL.

The Radioactive Effluent Release Report to be submitted 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.

The Radioactive Effluent Release Reports shall include the following information for each class of solid waste (as defined by 10 gfF"Part 61) shipped offsite during the report period:

a. Container volume,

b. Total curie quantity (specify whether determined by measurement or estimate),

c. Principal radionuclides (specify whether determined by measurement or estimate),

d. Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),

e. Type of container (e.g., LSA, Type A, Type B, Large Quantity), and

f. Solidification agent or absorbent (e.g., cement, urea formald~yde).

ibii'In lieu of submission with the first half year Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

SALEM - UN IT 2 6-20 <J..C Amendment No.

ADMINISTRATIVE CONTROLS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (continued)

The Radioactive Effluent Release Reports shall include a list of descriptio~

of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.

The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification 3.12.2.

-Je 5'fEE -:CAJ~Efe'f"~

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555, with a copy to the Administrato)~~he RegieAal Office within the time period specified for each report. !2-e~ i°()" I' 6.10 RECORD RETENTION In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be re~ined for at least the minimum period indicated. /a:

6 .10 .1 The fo 11 owing records sha 11 be retained for at 1east five years:

a. Records and logs of unit operation covering time interval at each power level.

b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety. (fffYe1t1rD .

c. t/1- REPORTABLE COcCllRRENC[$) submitted to the Cammi ssion.

d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

cc. itecel"es ef l"eactel" t9sts aFIEi e>ceel"ime~

~ Records of changes made to Operating Procedures required by Specification 6.8.1.

~ Records of radioactive shipments.

<ifr,. Records of sealed source and fission detector leak tests and results.

~- Records of annual physical inventory of all of record.

seal~d source material SALEM - UN IT 2 6-2'1?. 7 Amendment No.

INSERT TO SECTION 6.9.1 RADIAL PEAKING FACTOR LIMIT REPORT RTP 6.9.1.9 The F limits for Rated Thermal Power (F ) for all xy xy core planes containing bank "D" control rods and all unrodded core planes and the plot of predicted heat flux hot channel factor times relative power (F~*PREL) vs. Axial Core Height with the limit envelope shall be provided to the NRG Document Control Desk with copies to the Regional Administrator and the Resident Inspector. The Report shall be provided to the Commission no later than thirty days subsequent to initial use of F limits for xy surveillance unless otherwise approved by the Commission by letter.

In addition, in the event that the limit should change, requiring a new submittal or an amended submittal to the Peaking Factor Limit Report, it will be submitted within thirty days of the date the limit would become effective unless otherwise approved by the Commission by letter.

RTP Any information needed to support F will be by request from the NRG and xy need not be included in this report.

ADMINISTRATIVE CONTROLS 6.10.2 The following records shall be retained for the duration of the Unit Operating License:

a. Records and drawing changes reflecting unit design modifications

b.

made to systems and equipment described in the Final Safety Analysis Report.

Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

c. Records of radiation exposure for all individuals entering radiation control areas.

d. Records of gaseous and liquid radioactive material released to the environs.

e. Records of transient or operational cycles for those facility components identified in Table 5.7-1.

f. Records of reactor tests and experiments.

g. Records of training and qualification for current members of the plant staff.

h. Records of in-service inspections performed pursuant to these

Technical Specifications. .

i. Records of Quality Assurance activities requiredb'y the QA Manual.

j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments ursuan R 50.59. a.cfNih<?c; o~ 051? (_qno/. l'P'leef1'll9S' ~ ;fs predece!:>or,, -ff,,.. Nu~feQ.r f?ei1lew Esoqrd},

k. Records of meetings of the SORC and the NRB.

1. Records for Environmental Qualification which are covered under the provisions of Paragraph 2.C(7) and 2.C(S) of Facility Operating License DPR-75.

m. Records of the service lives of all hydraulic and mechanical snubbers including the date at which the service life conmences and associa-ted installation and maintenance records.

n. Records of secondary water sampling and water quality.

o. Records of analyses required by the radiological environmental monitoring program which would permit evaluation of the accuracy of the analysis at a later date. This should include procedures effective at specified times and QA records showing that these procedures were followed.

SALEM - UNIT 2 Amendment No.~

ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.l In lieu of the "control device" or "alarm signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20, each high radiation area in which the intensity of radiation is greater than 100 mremjhr but less than 1000 mrem/h~shall be barricaded and conspicuously posted as a High Radiation Area and entrance thereto shall be controlled by issuance of a Radiation Exposure

@) Permi~. Any individual or group of individuals permitted to enter such areas shall e provided with or accompanied by one or more of the following:

r-~--:--~-:---:-~~J

~-F .;/.,~ hr~~ ro.d*'afiM A radiation monitoring device which continuously indicates the a reec i5 es,fq hli'sW a*

radiation dose rate in the area.

fO r e.. period oF

'30 oftty~ or /et;t;I b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated J~ reef ~uNe>/lk<

preve td i;!naufh - may be made after the dose rate level in the area has been 17 r~-:r@ol tud*ry fYlttj established and personnel have been made knowledgeable of them. Qe used i nG+et<c./ c. A health physics qualified individual (i.e., qualified in radiation () -F Hie a.c.c.e~5 _, I protection procedures) with a radiation dose rate monitoring device {~ of. esc:.r11Rd who is responsible for providing positive control over the c r-R activities within the area and shall perform periodic radiation

a. I Pi?r ;),()Ci surveillance at the frequency specified by the faeility MealtB It> C.. FR ~o. ;;20 3 ) Pbysieise is tfie Radiation Work Permit.

(c.)(J.)(;;;)l'-1 , 6.12.2 In addition to the req~~ements of 6.12.1, areas accessible to personnel with radiation level~such that a major portion of the body could receive in one hour a dose greater than 1000 mrem shall be provided with locked doors to prevent unauthorized entr , and the keys shall be maintained un er the administrative control of the Senior Shift Supervisor on duty and/or Senior Supervisor - Radiation Protection. Doors shall remain locked except during periods of access by personnel under an approved Radiation Work Permit which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area. For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose in excess of 1000 mremti'that are located within large areas, such as PWR. containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonable constructed around the individual areas, then that area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device. In lieu of the stay time specification of the RWP, direct or remote (such as use of closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure cont ol over the activities within the area. fro111'cfqof f/,..._f ey a.rr- o erwi~e 'i?.o.ef*qfiop ?/'l:)fec.f iori Foflow;11 ra.dt.... fi'orl fl'oot@cf1'0n I ' proceecde..$ Health Physics- ersonnel or personne escorted by -Health Physies personnel fiH-eYJf-'-y shall be exempt from the RWP issuance requirement during the performance of i'rif-o their assigned radiation ro ection duties ::;,~f,- -t-rlt:s is f>OT'Mt:dly it'le, q > fie /@vtZ/ q-f "- c:l:s fei.Me o-F I~ l11c ~~ .fr.,,...., +he so~rc.e fi *~ 0 ' '1 0 r a.c.cesG; bff? su r+et,~ SALEM - UNIT 2 Amendment No. ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation. 6.13.2 Licensee initiated changes to the PCP:

1. Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change(s) was made. This submittal shall contain:

a. Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information;

b. A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and

c. Documentation of the fact that the change has been reviewed and found acceptable by the SORC.

2. Shall become effective upon review and acceptance by the SORC.

6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation. 6.14.2 Licensee initiated changes to the ODCM:

1. Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change(s) was made. This submittal shall contain:

a. Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information. Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change(s);

b. A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determination; and

c. Documentation of the fact that the change has been reviewed and found acceptable by the SORC.

2. Shall become effective upon review and acceptance by the SORC.

f§f MeastAremel'lt ma!:; at 18 11 fl" em se1:11"ee ef l"aeli eaeti 'o'i ~ SALEM - UNIT 2 6-M-30 Amendment No. ADMINISTRATIVE CONTROLS 6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS

6.15.1 Licensee initiated major changes to the radioactive waste system (liquid, gaseous and solid):

1. Shall be reported to the Commission in th~AR for the period in which the evaluation was reviewed by (SORC). The discussion of each chang;fshall contain: G[.:j- Tl'c~qhi?J

a. A summary of the evaluation that l~o the determinationJ..could be made in accordance with l(}F~0.59;

b. Sufficient detailed information to totally support the reason for the change without benefit of additional -or supplemental information;

c. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems;

d. An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto;

e. An evaluation of the change, which shows the expected maximum exposures to individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto;

f. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made;

g. An estimate of the exposure to plant operating personnel as a result of the change; and

h. Do~umentation of the fact that the change was reviewed and found acceptable by the (SORC).

2. Shall become effe~tive upon.review and acceptance by the SORC.

SALEM - UN IT 2 6-2-5 '3 ( Amendment No. UNIT 2 RETYPED PAGES __J

DEFINITIONS SECTION 1.0 DEFINITIONS DEFINED TERMS 1-1 ACTION . . . . 1-1 AXIAL FLUX DIFFERENCE 1-1 CHANNEL CALIBRATION 1-1 CHANNEL CHECK 1-1 CHANNEL FUNCTIONAL TEST 1-1 CONTAINMENT INTEGRITY 1-2 CONTROLLED LEAKAGE . . 1-2 CORE ALTERATION 1-2 QOSE EQUIVALENT I-131 1-2 E-AVERAGE DISINTEGRATION ENERGY 1-3 ENGINEERED SAFETY FEATURE RESPONSE TIME 1-3 FREQUENCY NOTATION . . . . . . . . 1-3 GASEOUS RADWASTE TREATMENT SYSTEM 1-3 IDENTIFIED LEAKAGE . . . . . . . . 1-3 MEMBER(S) OF THE PUBLIC . . . . 1-4 OFFSITE DOSE CALCULATION MANUAL (ODCM) 1-4 OPERABLE - OPERABILITY 1-4 OPERATIONAL MODE . . . . . 1-4 PHYSICS TESTS . . . . . . 1-5 PRESSURE BOUNDARY LEAKAGE 1-5 PROCESS CONTROL PROGRAM (PCP) 1-5 PURGE-PURGING . . . . . . 1-5 QUADRANT POWER TILT RATIO 1-5 RATED THERMAL POWER 1-5 REACTOR TRIP SYSTEM RESPONSE TIME 1-6 REPORTABLE EVENT 1-6 SHUTDOWN MARGIN 1-6 SITE BOUNDARY 1-6 SOLIDIFICATION . 1-6 SOURCE CHECK . . 1-6 STAGGERED TEST BASIS 1-6 THERMAL POWER 1-7 UNIDENTIFIED LEAKAGE 1-7 UNRESTRICTED AREA 1-7 VENTILATION EXHAUST TREATMENT SYSTEM 1-7 VENTING 1-7

SALEM - UNIT 2 I Amendment No.

ADMINISTRATIVE CONTROLS SECTION 6.1 RESPONSIBILITY 6-1 6.2 ORGANIZATION Onsite and Offsite Organizations 6-1 Facility Staff . . 6-1 Shift Technical Advisor 6-7 6.3 FACILITY STAFF QUALIFICATIONS 6-7 6.4 TRAINING . . . . . . . . . . . . . . . . . . . . . . 6-7 6.5 REVIEW AND AUDIT 6.5.l STATION OPERATIONS REVIEW COMMITTEE

Function Composition Alternates Meeting Frequency Quorum . . . . .

6-8 6-8 6-8 6-8 6-8 Responsibilities 6-9 SORG Review Process 6-10 Authority . . . . . 6-10 Records and Reports 6-10 6.5.2 NUCLEAR SAFETY REVIEW Function 6-10 Composition 6-10 Consultants 6-11 Off-Site Review (OSR) 6-11 Function 6-11 Review 6-12 Audits 6-12 Records and Reports 6-13 On-Site Safety Review Group (SRG) 6-13 Function . . . . 6-13 Responsibilities 6-14 Authority . . . . 6-14 SALEM - UNIT 2 XVIII Amendment No.

ADMINISTRATIVE CONTROLS SECTION 6.5.3 TECHNICAL REVIEW AND CONTROL 6-15 6.6 REPORTABLE EVENT ACTION 6-15 6.7 SAFETY LIMIT VIOLATION 6-16 6.8 PROCEDURES AND PROGRAMS 6-16 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS 6-19 6.9.2 SPECIAL REPORTS 6-23 6.10 RECORD RETENTION 6-23 6.11 RADIATION PROTECTION PROGRAM 6-25 6.12 HIGH RADIATION AREA . . 6-25 6.13 PROCESS CONTROL PROGRAM 6-26 6.14 OFFSITE DOSE CALCULATION MANUAL 6-27 6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID. GASEOUS AND SOLID WASTE TREATMENT SYSTEMS . . . . . . 6-27

SALEM - UNIT 2 XIX Amendment No.

DEFINITIONS

REACTOR TRIP SYSTEM RESPONSE TIME 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until loss of stationary gripper coil voltage.

REPORTABLE EVENT 1.27 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50. SHUTDOWN MARGIN 1.28 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all full length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn. SITE BOUNDARY 1.29 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee, as shown in Figure 5.1-3, and which defines the exclusion area as shown in Figure 5.1-1. SOLIDIFICATION 1.30 SOLIDIFICATION shall be the conversion of wet radioactive wastes into a form that meets shipping and burial ground requirements. SOURCE CHECK 1.31 SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity. STAGGERED TEST BASIS 1.32 A STAGGERED TEST BASIS shall consist of:

a. A test schedule for (n) systems, subsystems, trains, or other designated components obtained by dividing the specified test interval into (n) equal subintervals, SALEM - UNIT 2 1-6 Amendment No.

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS

4.2.2.1 4.2.2.2 a.

The provisions of Specification 4.0.4 are not applicable. F xy shall be evaluated to determine if FQ(Z) is within its limit by: Using the movable incore detectors to obtain a power distribution map at any THERMAL POWER greater than 5% of RATED THERMAL POWER.

b. Increasing the measured F component of the power distribution map xy by 3% to account for manufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties.

c. Comparing the F computed (Fe ) obtained in b, above to:

xy xy

1. The F limits for RATED THERMAL POWER (FRT) for the xy xy appropriate measured core planes given in e. and f.,

below, and

2. The relationship:

FL FRTP [l + 0.3(1-P)] xy xy L where F is the limit for fractional THERMAL POWER xy operation expressed as a function of FRTP and P is the xy fraction of RATED THERMAL POWER at which F was measured. xy

d. Remeasuring F according to the following schedule:

xy

1. When F C is greater than the FRTP limit for the appropriate xy xy measured core plane but less than the F L relationship, xy additional power distribution maps shall be taken and F C xy compared to FRTP and F L:

xy xy a) Either within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding by 20% of RATED THERMAL POWER or greater, the THERMAL POWER at which FC xy was last determined, or SALEM - UNIT 2 3/4 2-6 Amendment No. POWER DISTRIBUTION LIMITS SURVEILLANCE REOUIREMENTS(Continued) b) At least once per 31 EFPD, whichever occurs first.

2. When the Fe is less than or equal to the FRTPlimit for the xy xy appropriate measured core plane, additional power distribution C RTP L maps shall be taken and F compared to F and F at least xy xy xy once per 31 EFPD.

e. The F limit for Rated Thermal Power (FRTP) shall be provided for xy xy all core planes containing bank "D" control rods and all unrodded core planes in a Radial Peaking Factor Limit Report per specification 6.9.1.9.

f. The F limits of e, above, are not applicable in the following core xy plane regions as measured in percent of core height from the bottom of the fuel:

1. Lower core region from 0 to 15% inclusive.

2. Upper core region from 85 to 100%, inclusive.

3. Grid plane regions at 17.8 +/- 2%, 32.1 +/- 2%, 46.4 +/- 2%,

60.6 +/- 2% and 74.9 +/- 2% inclusive.

4. Core plane regions within+/- 2% of core height (+/- 2.88 inches) about the bank demand position of the bank "D" control rods.

g. Evaluating the effects of F on FQ(Z) to determine within its limit whenever F cY exceeds F L

xy xy 4.2.2.3 When FQ(Z) is measured pursuant to specification 4.10.2.2, an overall measured FQ(Z) shall be obtained from a power distribution map and increased by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty .

SALEM - UNIT 2 3/4 2-7 Amendment No.

INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm/ trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM). APPLICABILITY: At all times. ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable or change the setpoint so it is acceptably conservative.

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12. Exert best efforts to return the instrument to operable status within 30 days and, if unsuccessful, explain in the next semiannual radioactive effluent release report why the inoperability was not corrected in a timely manner.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.8 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-12. SALEM - UNIT 2 3/4 3-53 Amendment No. INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive gaseous effluent Monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm/ trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with the ODCM. APPLICABILITY: As shown in Table 3.3-13 ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable or change the setpoint so it is acceptably conservative.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13. Exert best efforts to return the instrument to operable status within 30 days and, if unsuccessful, explain in the next semi-annual radioactive effluent release report why the inoperability was not corrected in a timely manner.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, AND CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-13. SALEM - UNIT 2 3/4 3-59 Amendment No. REACTOR COOLANT SYSTEM 3/4.4.9 SPECIFIC ACTIVITY

LIMITING CONDITION FOR OPERATION 3.4.9 a.

The specific activity of the primary coolant shall be limited to: Less than or equal to 1.0 Ci/gram DOSE EQUIVALENT I-131, and

b. Less than or equal to 100/E Ci/gram.

APPLICABILITY: MODES 1, 2, 3, 4 and 5. ACTION: MODES 1, 2 and 3*

a. With the specific activity of the primary coolant >1.0 Ci/gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval or exceeding the limit line shown on Figure 3.4-1, be in at least HOT STANDBY with T < 500°F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . avg

b. With the specific activity of the primary coolant >100/E Ci/gram, be in at least HOT STANDBY with T <500°F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . avg MODES 1, 2, 3, 4 and 5

a. With the specific activity of the primary coolant great~r than 1.0 Ci/gram DOSE EQUIVALENT I-131 or greater than 100/E Ci/gram, perform the sampling and analysis requirements of item 4a of Table 4.4-2 until the specific activity of the primary coolant is restored to within its limits.

SURVEILLANCE REQUIREMENTS 4.4.9 The specific activity of the primary coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-4.

With T >

avg - 500°F. SALEM - UNIT 2 3/4 4-23 Amendment No. INTENTIONALLY LEFT BLANK SALEM - UNIT 2 3/4 4-24 Amendment No. RADIOACTIVE EFFLUENTS

LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, and

b. During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.

APPLICABILITY: At all times. ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits .

b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents shall be determined in accordance with the ODCM at least once per 31 days. SALEM - UNIT 2 3/4 11-5 Amendment No. RADIOACTIVE EFFLUENTS LIQUID RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.1.3 The liquid radwaste treatment system shall be used to reduce the radioactive materials liquid wastes prior to their discharge when the projected cumulative doses due to the liquid effluent from each reactor to UNRESTRICTED AREAS (see Figure 5.1-3) exceed 0.375 mrem to the total body or 1.25 mrem to any organ during any calendar quarter. APPLICABILITY: At all times. ACTION:

a. With the radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that includes the following information:

1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability.

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action(s) taken to prevent a recurrence.

b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.3 Doses due to liquid releases shall be projected at least once per 31 days in accordance with the ODGM. SALEM - UNIT 2 3/4 11-6 Amendment No. RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site areas and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or. equal to 10 mrad for beta radiation and,

b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILITY: At all times. ACTION:

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any 6f the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the release and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with the ODCM at least once per 31 days. SALEM - UNIT 2 3/4 11-12 Amendment No. RADIOACTIVE EFFLUENTS DOSE - IODINE-131, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from iodine-131, from tritium, and from all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ and,

b. During any calendar year: Less than or equal to 15 mrems to any organ.

APPLICABILITY: At all times. ACTION:

a. With the calculated air dose from the release of iodine-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the release and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the ODCM at least once per 31 days. SALEM - UNIT 2 3/4 11-13 Amendment No. RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases, from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3), exceed 0.625 mrad for gamma radiation and 1.25 mrad for beta radiation in any calendar quarter. The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases, from each reactor unit, from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) would exceed 1.875 mrem to any organ in any calendar quarter. APPLICABILITY: At all times. ACTION:

a. With gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that includes the following information:

1. Explanation of why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action(s) taken to prevent a recurrence.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.4 Doses due to gaseous releases from the site shall be projected at least once per 31 days in accordance with the ODCM. SALEM - UNIT 2 3/4 11-14 Amendment No. SOLID RADIOACTIVE WASTE LIMITING CONDITION FOR OPERATION

3.11.3. The solid radwaste system shall be used in accordance with a PROCESS CONTROL PROGRAM to process wet radioactive waste to meet shipping and burial ground requirements.

APPLICABILITY: At all times. ACTION:

a. With the provisions of the PROCESS CONTROL PROGRAM not satisfied, suspend shipments of defectively processed or defectively packaged solid radioactive wastes from the site.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.3. The PROCESS CONTROL PROGRAM shall be used to verify the SOLIDIFICATION of at least one representative test specimen from at least every tenth batch of each type of wet radioactive waste (e.g., filter sludges, spent resins, evaporator bottoms, boric acid solutions, and sodium sulfate solutions).

a. If any test specimen fails to verify SOLIDIFICATION, the SOLIDIFICATION of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative SOLIDIFICATION parameters can be determined in accordance with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION. SOLIDIFICATION of the batch may then be resumed using the alternative SOLIDIFICATION parameters determined by the PROCESS CONTROL PROGRAM.

b. If the initial test specimen from a batch of waste fails to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall provide for the collection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least three consecutive initial test specimens demonstrate SOLIDIFICATION. The PROCESS CONTROL PROGRAM shall be modified as required, as provided

in Specification 6.13, to assure SOLIDIFICATION of subsequent batches of waste .

SALEM - UNIT 2 3/4 11-17 Amendment No.

RADIOACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE

LIMITING CONDITION FOR OPERATION 3.11.4. The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrems).

APPLICABILITY: At all times ACTION:

a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specification 3.11.l.2a, 3.11.l.2b, 3.ll.2.2a, 3.11.2.2b, 3.11.2.3a, or 3.ll.2.3b, calculations should be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the limits of this Specification have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report.

It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action an the request is complete .

SALEM - UNIT 2 3/4 11-18 Amendment No.

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM

LIMITING CONDITION FOR OPERATION 3.12.1. The radiological environmental monitoring program shall be conducted as specified in Table 3.12-1.

APPLICABILITY: At all times. ACTION:

a. With the radiological environmental monitoring program not being conducted as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Specification 6.9.1.7, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2, and 3.11.2.3. When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1) + concentration (2) + ... 1.0 reporting level (1) reporting level (2) When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a member of the public is equal to or greater

SALEM - UNIT 2 3/4 12-1 Amendment No.

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM

LIMITING CONDITION FOR OPERATION ACTION: (Cont'd) than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2, and 3.11.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.12-1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days. The specific locations from which samples were unavailable may then be deleted from the monitoring program.

Pursuant to Specification 6.9.1.8, identify the cause of the unavailability of samples and the new location(s) for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report. Include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

d. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the locations specified in the ODCM and shall be analyzed pursuant to the requirements of Table 4.12-1 .

SALEM - UNIT 2 3/4 12-2 Amendment No.

TABLE 3.12-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Water Airborne Particul~te Fish Milk Food Products Anal;:l:sis (12CiL12 or Gases (J;!CiLm 2 (12CUKg. wet} (12Cill) (12CUKg. wet}

4 H-3 2 x 10 (*) 4 Mn-54 1 x 103 3 x 10 Fe-59 4 x 102 4 1 x 10 3 4 Co-58 1 x 10 3 x 10 Co-60 2 4 3 x 10 1 x 10 2 4 Zn-65 3 x 10 2 x 10 2 Zr-Nb-95 4 x 10 I-131 2 0.9 3 1 x {02 Cs-134 3 3 30 10 1 x 10 60 1 x 10 Cs-137 so 3 3 20 2 x 10 70 2 x 10 2 2 Ba-La-140 2 x 10 3 x 10 (*) For drinking wate4 samples. This is a 40CFR141 value. If no drinking water pathway exists, a value of 3 x 10 pCi/l may be used. SALEM - UNIT 2 3/4 12-8 Amendment No. TABLE 4.12-1 MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION (LLD)a,b Water Airborne Particul~te Fish Milk Food Products Sediment Analysis (:QCil'.'.12 or Gases (:QCil'.'.m 2 (:QCil'.'.Kg, wet} (:QCil'.'.1} (:QCil'.'.Kg, wet} (:QCil'.'.Kg dry} I gross beta 4 1 x 10- 2 H-3 2000c Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-Nb-95 15 ld 2 I-131 7 x 10- 1 60 2 Cs-134 15 5 x 10- 130 15 60 150 2 Cs-137 18 6 x 10- 150 18 80 180 Ba-La-140 15 15 SALEM - UNIT 2 3/4 12-9 Amendment No. TABLE 4.12-1 (Cont'd) TABLE NOTATION a Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13, Rev. 1, July, 1977. b The LLD is defined in Table 4.11-1. c If no drinking water pathway exists, a value of 3000 pCi/l may be used. d LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used. SALEM - UNIT 2 3/4 12-10 Amendment No. L RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2. A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk 1nimal, t2e nearest residence and the nearest garden* of greater than 50 m (500 ft ) producing broad leaf vegetation. (For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify within a distance of 5 km (3 miles) the locations in each of the 16 ~eteorological sectors of all milk animals and all gardens of greater than 50 m producing broad leaf vegetation. APPLICABILITY: At all times. ACTION:

a. With a land use census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, identify the new location(s) in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.8.

b. With a land use census identifying a location(s) that yields a calculated dose or dose commitment (via) the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, add the new location(s) to the radiological environmental monitoring program within 30 days. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s) (via the same exposure pathway) may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted. Pursuant to Specification 6.9.1.8, identify the new location(s) in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Q in lieu of the garden census.

Specifications for broadleaf vegetation sampling in Table 3.12-l.4c shall be followed, including analysis of control samples .

SALEM - UNIT 2 3/4 12-11 Amendment No.

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS (Cont'd) SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7. SALEM - UNIT 2 3/4 12-12 Amendment No. RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3. INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission. APPLICABILITY: At all times. ACTION:

a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7.

b. The provisions of Specifications 3.0.3 and 3.0.4. are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.3 A summary of the results obtained as part of the above required Interlaboratory Comparison Program and in accordance with the ODCM shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7. SALEM - UNIT 2 3/4 12-13 Amendment No. POWER DISTRIBUTION LIMITS event. The penalties applied to F H to account for Rod Bow (Figure 3.2-4) as a function of burnup are consistent with those described in Mr. John F. Stolz's (NRG) letter to T. M. Anderson (Westinghouse) dated April 5, 1979 and W 8691 Rev. 1 (partial rod bow test data). When an FQ measurement is taken, an allowance for both experimental error and manufacturing tolerance must be made. An allowance of 5% is appropriate for a full core map taken with the incore detector flux mapping system and a 3% allowance is appropriate for manufacturing tolerance. When RCS flow rate and F H are measured, no additional allowances are necessary prior to comparison with the limits of Figure 3.2-3. Measurement errors of 3.5% for RCS total flow rate and 4% for F H have been allowed for in determination of the design DNBR value. The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months period surveillance of indicated RCS flow is sufficient to detect any flow degradation which could lead to operation outside the acceptable region of operation shown in Figure 3.2-3. The radial peaking factor F (z) is measured periodically to provide assurance xy that the hot channel factor, FQ(Z), remains within its limit. The F limit xy for RATED THERMAL POWER (FRTP), as provided in the Radial Peaking Factor Limit xy Report per specification 6.9.1.9, was determined from expected power control maneuvers over the full range of burnup conditions in the core. 3/4.2.4 QUADRANT POWER TILT RATIO The quadrant power tilt ratio limit assures that the radial power distribution satisfies the design values used in the power capability analysis. Radial power distribution measurements are made during startup testing and periodically during power operation. SALEM - UNIT 2 B 3/4 2-5 Amendment No. REACTOR COOLANT SYSTEM BASES

3/4.4.9 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the resulting 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months doses at the site boundary will not exceed an appropriately small fraction of Part 100 limits following a steam generator tube rupture accident in conjunction with an assumed steady state primary-to-secondary steam generator leakage rate of 1.0 GPM. The values for the limits on specific activity represent interim limits based upon a parametric evaluation by the NRG of typical site locations. These values are conservative in that specific site parameters of the Salem site, such as site boundary location and meteorological conditions, were not considered in this evaluation. The NRG is finalizing site specific criteria which will be used as the basis for the reevaluation of the specific activity limits of this site. This reevaluation may result in higher limits.

Reducing T to less than 500°F prevents the release of activity should a steam generat3~gtube rupture since the saturation pressure of the primary coolant is below the lift pressure of the atmospheric steam relief valves. The surveillance requirements provide adequate assurance that excessive specific activity levels in the primary coolant will be detected in sufficient time to take corrective action. Information obtained on iodine spiking will be used to assess the parameters associated with spiking phenomena. A reduction in frequency of isotopic analyses following power changes may be permissible if justified by the data obtained .

SALEM - UNIT 2 B 3/4 4-6 Amendment No.

6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY

6.1.1 The General Manager - Salem Operations shall be responsible for overall facility operation and shall delegate, in writing, the succession to this responsibility during his absence.

6.1.2 The Senior Nuclear Shift Supervisor, or during his absence from the control room a designated individual, shall be responsible for the control room command function. A management directive to this effect, signed by the Vice President and Chief Nuclear Officer, shall be reissued to all station personnel on an annual basis. 6.2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include positions for activities affecting the safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shall be established and defined from the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the Salem Updated Final Safety Analysis Report and updated in accordance with 10 CFR 50.7l(e).

b. The General Manager - Salem Operations shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

c. The Vice President and Chief Nuclear Officer shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

d. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

6.2.2 FACILITY STAFF The facility organization shall be subject to the following:

a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1; SALEM - UNIT 2 6-1 Amendment No.

ADMINISTRATIVE CONTROLS FACILITY STAFF (continued)

b.

c. At least one licensed Reactor Operator shall be in the control room when fuel is in the reactor. In addition, at least one licensed Senior Reactor Operator shall be in the control room area at all times. All CORE ALTERATIONS shall be observed and directly supervised by a licensed Senior Reactor Operator who has no other concurrent responsibilities during this operation.

d. A site Fire Brigade of at least 5 members shall be maintained onsite at all times*. The Fire Brigade shall not include 4 members of the minimum shift crew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency.

e. The amount of overtime worked by plant staff members performing safety-related functions must be limited in accordance with the NRG Policy Statement on working hours (Generic Letter No. 82-12).

f. The Operations Manager, Operating Engineer, Senior Nuclear Shift Supervisor, and Nuclear Shift Supervisor shall each hold a senior reactor operator license. The Nuclear Control Operators shall hold reactor operator licenses.

The Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of Fire Brigade members provided immediate action is taken to restore the Fire Brigade to within the minimum requirements.

SALEM - UNIT 2 6-2 Amendment No. Figure 6.2-1 CORPORATE HEADQUARTERS AND OFF-SITE ORGANIZATION FOR MANAGEMENT AND TECHNICAL SUPPORT (Deleted)

SALEM - UNIT 2 6-3 Amendment No.

FIGURE 6.2 - 2 FACILITY ORGANIZATION (Deleted)

SALEM - UNIT 2 6-4 Amendment No.

TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION

POSITION SALEM UNIT 2 WITH UNIT 1 IN MODES 5 OR 6 OR DE-FUELED NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION MOVE3 l, 2: ' 3 & 4 MOVE3 5 & 6 SNSS la la SRO lb none STA lb none NCO 2 1 EO/UO 3 2c Maintenance Electrician 1 none la a,e Rad. Pro. Technician 1 WITH UNIT 1 IN MODES 1, 2, 3 OR 4 POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION MODES 1, 2, 3 & 4 MODES 5 & 6 SNSS SRO none STA none NCO 1 EO/UO 1 Maintenance Electrician none Rad. Pro. Technician la

~/ Individual may fill the same position on Unit 1 ~/ Individual who fulfills the STA requirement may fill the same position on Unit 1. The STA, if a licensed SRO, may concurrently fill the SRO position on one unit; the other unit also requires a qualified SRO on shift. £/ One of the two required individuals may fill the position on Unit 1, such that there are a total of three EO/UO's for both units. ~/ One of the three required individuals may fill the same position of Unit 1, such that there are a total of five EO/UO's for both units .

g/ Not needed if both reactors are de-fueled.

SALEM - UNIT 2 6-5 Amendment No. TABLE 6.2-1 (Continued) SNSS - Senior Nuclear Shift Supervisor with a Senior Reactor Operator License on both units. SRO Individual with a Senior Reactor Operator License on both units (normally, a Nuclear Shift Supervisor). NCO Nuclear Control Operator with a Reactor Operator License on both units. STA Shift Technical Advisor (if licensed as SRO, may be assigned duties as a Nuclear Shift Supervisor). EO/UO- Equipment Operator or Utility Operator. Except for the Senior Nuclear Shift Supervisor, the Shift Crew Composition may be one less than the minimum requirements of Table 6.2-1 for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate the unexpected absence of on-duty shift crew members provided that immediate action is taken to restore the Shift Crew Composition to within the minimum requirements of Table 6.2-1. This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewperson's being late or absent. During any absence of the Senior Nuclear Shift Supervisor from the Control Room area while the unit is in any MODE, an individual with a valid SRO License shall be designated to assume the Control Room command function. SALEM - UNIT 2 6-6 Amendment No. ADMINISTRATIVE CONTROLS 6.2.3 SHIFT TECHNICAL ADVISOR 6.2.3.1 The Shift Technical Advisor shall serve in an advisory capacity to the Senior Nuclear Shift Supervisor on matters pertaining to the engineering aspects assuring safe operation of the unit. 6.2.3.2 The Shift Technical Advisor shall have a Bachelor's Degree or equivalent in a scientific or engineering discipline with specific training in plant design and response and analysis of the plant for transients and accidents. 6.3 FACILITY STAFF QUALIFICATIONS 6.3.l Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI Nl8.l-1971 for comparable positions and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRG letter to all licensees, except for the Radiation Protection Engineer or Radiation Protection/Chemistry Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. 6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be coordinated by each functional level manager (Department Head) at the facility and maintained under the direction of the Manager - Nuclear Training and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI Nl8.l-1971 and 10 CFR Part 55. 6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Manager - Site Protection and shall meet or exceed the requirements of Section 27 of NFPA Code-1975, except for Fire Brigade training sessions which shall be held at least quarterly. SALEM - UNIT 2 6-7 Amendment No. ADMINISTRATIVE CONTROLS 6.5 REVIEW AND AUDIT 6.5.l STATION OPERATIONS REVIEW COMMITTEE (SORG) FUNCTION 6.5.1.l The Station Operations Review Committee shall function to advise the General Manager - Salem Operations on operational matters related to nuclear safety. COMPOSITION 6.5.1.2 The Station Operations Review Committee (SORG) shall be composed of: Chairman: General Manager - Salem Operations Member and Vice Chairman: Maintenance Manager Member and Vice Chairman: Operations Manager Member and Vice Chairman: Technical Manager Member: Radiation Protection/Chemistry Manager Member: Radiation Protection Engineer Member: Chemistry Engineer Member: Maintenance Engineers Member: Operating Engineers Member: Technical Engineers (Group Heads) Member: Onsite Safety Review Engineer ALTERNATES 6.5.1.3 Alternates:

a. Alternates shall be appointed by the SORG Chairman in writing.

b. Only designated Vice Chairmen may act as Chairman of a SORG meeting in the absence of the General Manager - Salem Operations.

c. The Senior Nuclear Shift Supervisor (SNSS) may act as an alternate for the Operations Manager or an Operating Eng~neer. The SNSS may also act as an alternate when the Operations Manager is acting as Chairman.

MEETING FREQUENCY 6.5.1.4 The SORG shall meet at least once per calendar month and as convened by the SORG Chairman or his designated alternate. QUORUM 6.5.1.5 The minimum quorum of the SORG necessary for the performance of the SORG responsibility and authority provisions of these technical specifications shall consist of the Chairman or his designated alternate and five members including alternates. SALEM - UNIT 2 6-8 Amendment No. ADMINISTRATIVE CONTROLS QUORUM (continued)

a.

b. No more than two members or one member and one alternate from any individual department will make up part of the voting quorum. If the Chairman for a meeting is a Vice Chairman, then up to two additional members (or one member and one alternate) may be part of the voting quorum. RESPONSIBILITIES 6.5.1.6 The Station Operations Review Committee shall be responsible for:

a. Review of: (1) Station Administrative Procedures and changes thereto and (2) Newly created procedures or changes to existing procedures that require a 10CFR50.59 safety evaluation as described in Section 6.5.3.2.d.

b. Review of all proposed tests and experiments that affect nuclear safety.

c. Review of all proposed changes to Appendix "A" Technical Specifications.

d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety .

e.

f. Review of the safety evaluations that have been completed under the provisions of 10 CFR 50.59. Initiation or review of investigations of all violations of the Technical Specifications including the reports covering evaluation and recommendations to prevent recurrence.

g. Review of all REPORTABLE EVENTS.

h. Review of facility operations, as determined by the SORG Chairman, to detect potential nuclear safety hazards.

i. Performance of special reviews, investigations or analyses and reports thereon as determined by the SORG.

j. Review of the Facility Security Plan and implementing procedures and changes thereto.

k. Review of the Facility Emergency Plan and implementing procedures and changes thereto that require a 10CFR50.59 evaluation, or involve a potential decrease in the effectiveness of the plan, per 10CFR50.54(q). as described in Section 6.5.3.2.d.

1. Review of the Fire Protection Program and implementing procedures and changes thereto that require a 10CFR50.59 safety evaluation .

SALEM - UNIT 2 6-9 Amendment No. ADMINISTRATIVE CONTROLS RESPONSIBILITIES (continued)

m.

n. Review of all unplanned on-site releases of radioactivity to the environs including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence. Review of changes to the PROCESS CONTROL MANUAL and the OFF-SITE DOSE CALCULATION MANUAL. SORG REVIEW PROCESS 6.5.1.7 A technical review and control system utilizing qualified reviewers shall function to perform the periodic or routine review of procedures and changes thereto. Details of this technical review process are provided in Section 6.5.3. AUTHORITY 6.5.1.8 The Station Operations Review Committee shall:

a. Provide recommendations to the General Manager - Salem Operations, indicating written approval or disapproval of items considered under 6.5.1.6 above.

b. Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Vice President and Chief Nuclear Officer and the General Manager - Quality Assurance and Nuclear Safety of disagreement between the SORG and the General Manager - Salem Operations; however, the General Manager

- Salem Operations shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above. RECORDS AND REPORTS 6.5.1.9 The Station Operations Review Committee shall maintain written minutes of each meeting and copies shall be provided to the Vice President and Chief Nuclear Officer, the General Manager - Quality Assurance and Nuclear Safety and the Manager - Nuclear Safety. 6.5.2 NUCLEAR SAFETY REVIEW FUNCTION 6.5.2.1 The Nuclear Safety Department shall function to provide the independent safety review program and audit of designated activities. COMPOSITION 6.5.2.2 The Nuclear Safety Department, under the cognizance of the General Manager - Quality Assurance and Nuclear Safety, shall consist of the Manager - Nuclear Safety, the Offsite Safety Review staff (OSR) and the Onsite Safety Review Group (SRG). The OSR staff and the SRG each consist of at least four

dedicated, full-time engineers.

SALEM - UNIT 2 6-10 Amendment No. ADMINISTRATIVE CONTROLS COMPOSITION (continued)

The Manager - Nuclear Safety and the Offsite Safety Review staffshall meet or exceed the qualifications described in Section 4.7 of ANS 3.1 - 1981 and shall be guided by the provisions for independent review described in Section 4.3 of ANSI Nl8.7 - 1976 (ANS 3.2).

The Offsite Safety Review staff shall generally possess experience and competence in the areas listed in Section 6.5.2.4.1. A system of qualified reviewers from other technical organizations may be used to augment OSR staff expertise in the disciplines of Section 6.5.2.4.1, where appropriate. Such qualified reviewers shall meet the same qualification requirements as the Offsite Safety Review Staff, and shall not have been involved with performance of the original work. The Onsite Safety Review Group staff shall meet or exceed the qualifications described in Section 4.4 of ANS 3.1 - 1981. CONSULTANTS 6.5.2.3 Consultants or other technical experts shall be utilized by the Nuclear Safety Department to the extent necessary. 6.5.2.4 OFF-SITE SAFETY REVIEW (OSR) FUNCTION 6.5.2.4.1 The OSR staff shall function to provide independent review and audit of designated activities in the areas of:

a. Nuclear Power Plant Operations

b. Nuclear Engineering

c. Chemistry and Radiochemistry

d. Metallurgy

e. Instrumentation and Control

f. Radiological Safety

g. Mechanical Engineering

h. Electrical Engineering

i. Quality Assurance j . Nondestructive Testing

k. Emergency Preparedness

SALEM - UNIT 2 6-11 Amendment No.

ADMINISTRATIVE CONTROLS REVIEW 6.5.2.4.2 The OSR shall review:

a. The safety evaluations for changes to procedures, equipment, or systems; and tests or experiments completed under the provisions of 10CFR50.59, to verify that such actions did not constitute an unreviewed safety question;

b. Proposed changes to procedures, equipment, or systems; and tests or experiments that involve an unreviewed safety question as defined in 10CFR50.59;