ML041110042

License Amendment Request Proposed Change to Relocate Administrative Control Requirements

ML041110042
Person / Time
Site:	Limerick
Issue date:	04/08/2004
From:	Gallagher M Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML041110042 (64)

Text

Exek( nm Exelon Nuclear www.exeloncorp.com Nulear 200 Exelon Way Kennett Square, PA 19348 10 CFR 50.90 April 8, 2004 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Limerick Generating Station, Units 1 and 2 Facility Operating License Nos. NPF-39 and NPF-85 NRC Docket Nos 5-352 and 50n-53

SUBJECT:

License Amendment Request Proposed Change to Relocate Administrative Control Requirements Pursuant to 10 CFR 50.90, "Application for amendment of license or construction permit,"

Exelon Generation Company, LLC (Exelon), hereby requests the following amendment to the Technical Specifications (TS), Appendix A of Operating License Nos. NPF-39 and NPF-85 for Limerick Generating Station (LGS), Units 1 and 2, respectively.

The proposed changes would relocate several TS Section 6, Administrative Control requirements to the Exelon Generation Company, LLC/AmerGen Energy Company, LLC, Quality Assurance Topical Report, the document controlling the Company's quality assurance program. Specifically, the amendment would relocate (1) the Plant Operations Review Committee and Nuclear Review Board requirements, (2) the program/procedure review and approval requirements, and (3) the record retention requirements.

The proposed changes are consistent with the recommendations of NRC Administrative Letter 95-06, "Relocation of Technical Specification Administrative Controls Related to Quality Assurance," dated December 12, 1995. Additionally, the proposed changes conform to an improved standard TS presented in the NRC document titled: "Standard Technical Specifications - General Electric Plants, BWR/4," NUREG-1433, Rev. 2.

Exelon has concluded that the proposed changes present no significant hazards consideration under the standards set forth in 10CFR 50.92.

Exelon requests approval of the proposed amendment by April 8, 2005. Upon NRC approval, the amendment shall be implemented within 60 days of issuance.

1c

Proposed Change to Relocate Administrative Control Requirements April 8, 2004 Page 2 These proposed changes have been reviewed by the Plant Operations Review Committee, and approved by the Nuclear Safety Review Board.

We are notifying the State of Pennsylvania of this application for changes to the TS License by transmitting a copy of this letter and its attachments to the designated State Official.

If you have any questions or require additional information, please contact Doug Walker at (610) 765-5726.

I declare under penalty of perjury that the foregoing is true and correct.

Respectfully, Executed on of00z-Iq Michael P. Gallagher Director, Licensing & Regulatory Affairs Exelon Generation Company, LLC Attachments: 1. Evaluation of Proposed Changes

2. Technical Specifications Marked-Up Pages

3. Technical Specifications Typed Pages cc:

H. J. Miller, Administrator, Region I, USNRC A. L. Burritt, USNRC Senior Resident Inspector, LGS S. Wall, Project Manager, NRR USNRC R. R. Janati, Pennsylvania Department of Environmental Resources (w/enc)

ATTACHMENT I License Amendment Request Limerick Generating Station, Units 1 and 2 Docket Nos. 50-352 and 50-353 Evaluation of Proposed Changes to Relocate Administrative Control Requirements

ATTACHMENT I EVALUATION OF PROPOSED CHANGES TO RELOCATE ADMINISTRATIVE CONTROL REQUIREMENTS CONTENTS

2.0 PROPOSED CHANGE

S

5.0 REGULATORY ANALYSIS

5.1 No Significant Hazards Consideration 5.2 Applicable Regulatory Requirements/Criteria

7.0 REFERENCES

LGS Units 1&2: Relocation of Administrative Control Requirements Page 1 of 6 EVALUATION OF PROPOSED CHANGES

1.0 DESCRIPTION

The proposed changes would revise the Facility Operating Licenses Nos. NPF-39 and NPF-85 for Limerick Generating Station (LGS), Units 1 and 2, respectively. The changes would relocate the requirements of Technical Specification (TS) section 6.5, 'Review and Audit,"

sections 6.8.2 and 6.8.3, "Procedures and Programs," and section 6.10, "Record Retention," to the Exelon Generation Company, LLC (EGC)/AmerGen Energy Company, LLC, (AmerGen)

Quality Assurance Topical Report (QATR), the highest tiered document controlling the Company's quality assurance program. Future changes to these administrative requirements will be subject to the regulatory controls of 10 CFR 50.54(a). Accordingly, administrative improvements and clarifications, spelling errors, organizational title changes, as well as other changes that do not reduce the quality assurance program commitments, as described in 10 CFR 50.54(a), could be implemented without prior NRC approval. This will reduce the implementation time and resources spent by Exelon and NRC staff in the preparation and review of license amendment requests associated with these types of changes.

The proposed changes are consistent with the recommendations of NRC Administrative Letter 95-06, "Relocation of Technical Specification Administrative Controls Related to Quality Assurance," dated December 12, 1995. Additionally, the proposed changes conform to an improved TS presented in the NRC document titled: "Standard Technical Specifications -

General Electric Plants, BWR/4", NUREG-1433, Rev. 2.

2.0 PROPOSED CHANGE

Changes requested by this amendment application are:

1. Delete TS section 6.5.1, "Plant Operations Review Committee (PORC)." Licensee will relocate deleted requirements to the EGC/AmerGen Quality Assurance Topical Report (QATR). Specifically, sections 6.5.1.1 through 6.5.1.8, which are titled Function, Composition, Alternates, Meeting Frequency, Quorum, Responsibilities, and Records, will be relocated.

2. Delete TS section 6.5.2, "Nuclear Review Board (NRB)." Licensee will relocate deleted requirements to the EGC/AmerGen QATR. Specifically, sections 6.5.2.1 through 6.5.2.6, and 6.5.2.9, which are titled Function, Composition, Alternates, Consultants, Meeting Frequency, Quorum, and Records, will be relocated.

3. Delete TS section 6.5.3, "Program/Procedure Review and Approval." Licensee will relocate deleted requirements to the EGC/AmerGen QATR. This section describes the review and approval requirements for procedures and programs identified in TS section 6.8.1 (no changes to TS section 6.8.1 are proposed).

4. Delete TS section 6.8.2. This section references the procedure review and approval requirements described in the TS sections 6.5.1 and 6.5.3, proposed for deletion in changes I and 3 above. Licensee will relocate the deleted requirements to the EGC/AmerGen QATR.

LGS Units 1&2: Relocation of Attachment I Administrative Control Requirements Page 2 of 6

5. Delete TS section 6.8.3. This section describes the review and approval requirements for temporary changes to procedures. Licensee will relocate the deleted requirements to the EGC/AmerGen QATR.

6. Delete TS section 6.10, "Record Retention." This section describes the record retention requirements. Licensee will relocate the deleted requirements to the EGC/AmerGen QATR.

7. Delete the PCP record retention requirement in TS section 6.13.1, "Process Control Program." This requirement will be relocated to the EGC/AmerGen QATR as described in change 6 above.

8. Delete the ODCM record retention requirement in TS section 6.14.1.a, uOffsite Dose Calculation Manual." This requirement will be relocated to the EGC/AmerGen QATR as described in change 6 above.

The administrative control requirements identified above will be relocated intact to the QATR.

Subsequent changes to these requirements will be controlled in accordance with 10 CFR 50.54(a). Implementation of the amendment will be performed within 60 days of NRC issuance of the amendment. Relocation of these requirements will be completed on or before the implementation of the NRC approved License Amendment. In the absence of a bases section for TS Section 6.0, Administrative Controls, there are no Bases section changes proposed by this amendment application.

3.0 BACKGROUND

NRC regulatory requirements related to the content of the Technical Specifications (TS) are set forth in 10 CFR 50.36. That regulation requires that the TS include items in five specific categories, including (1) safety limits, limiting safety system settings and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; and (5) administrative controls. However, the regulation does not specify the particular requirements to be included in the plant's Tech Specs.

The NRC provided guidance for the contents of TS in its "Final Policy Statement on Technical Specifications Improvement for Nuclear Power Reactors, 58 FR 39132, July 22, 1993. In particular, the NRC indicated that certain items could be relocated from the TS to licensee-controlled documents. The Final Policy Statement identified future criteria to be used in determining whether particular safety functions are required to be include in the TS, as follows:

(1) installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary; (2) a process variable, design feature, or operating restriction that is an initial condition of a Design Basis Accident or Transient analysis that either assumes the failure of, or presents a challenge to the integrity of a fission product barrier; (3) a structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a Design Basis Accident or Transient that either assumes the failure of, or presents a challenge to the integrity of a fission product barrier; (4) a structure, system, or component which operating experience or probabilistic safety assessment has shown to be significant to public health and safety. The NRC adopted amendments to 10 CFR 50.36, (July 19, 1995) pursuant to which the rule was revised to codify and incorporate these criteria.

LGS Units 1&2: Relocation of Administrative Control Requirements Page 3 of 6 The NRC's policy statement provides that those existing TS Limiting Condition for Operation (LCOs) which do not satisfy these four specified criteria may be relocated to the Updated Final Safety Analysis Report (UFSAR), such that future changes could be made to these provisions pursuant to 10 CFR 50.59. Other requirements may be relocated to more appropriate documents (e.g., Security Plan, Quality Assurance Plan, and the Emergency Plan) and controlled by the applicable regulatory requirement. Similarly, while the required content of TS administrative controls is specified in 10 CFR 50.36(c)(5), particular details of administrative controls may be relocated to licensee controlled documents where section 50.54, 50.59, or other regulations provide adequate regulatory control.

While the criteria specifically apply to LCOs, in adopting the revision of the rule, the NRC indicated that the intent of these criteria can be utilized to identify the optimum set of administrative controls in the TS. Addressing administrative controls, 10 CFR 50.36 states that they are "the provisions relating to organization and management, procedures, record keeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner."

The specific content of the administrative controls section of the TS is, therefore, that information which the Commission deems essential for the safe operation of the facility, and which is not already adequately covered by other regulations. Accordingly, the NRC has determined that requirements that are not specifically required under 50.36(c)(5), and are not otherwise necessary to obviate the possibility of an abnormal situation, or event, giving rise to an immediate threat to the public health and safety, can be removed from the administrative controls section of the Technical Specifications.

4.0 TECHNICAL ANALYSIS

The proposed license amendment requests the relocation of several administrative control requirements from Technical Specifications (TS), Section 6, to the Exelon Generation Company, LLC (EGC)/AmerGen Energy Company, LLC (AmerGen) Quality Assurance Topical Report (QATR). This relocation applies to the onsite and offsite organization's review and audit requirements, the procedural review and approval requirements, and the record retention requirements.

As presented in the Background section above, the NRC staff concluded that Technical Specifications not specifically required under 50.36(c)(5), and not otherwise necessary to obviate the possibility of an abnormal situation, or event, giving rise to an immediate threat to the public health and safety, can be removed from administrative controls section of the Technical Specifications. Consistent with this policy position, the NRC staff issued Administrative Letter (AL) 95-06, December 12, 1995, identifying TS administrative control requirements that qualify for relocation to licensee quality assurance control documents subject to the controls of 10 CFR 50.54(a). Requirements identified by AL 95-06 included review and audit, procedure review and approval, and record retention requirements. The changes proposed herein conform to the NRC staff position presented in AL 95-06.

NRC approved NUREG-1433, "Standard Technical Specifications - General Electric Plants, BWR/4," Revision 2, identifies an improved TS that was developed based on the criteria in the "Final Commission Policy Statement on Technical Specifications Improvement for Nuclear Power Reactors," dated July 22, 1993, and subsequently codified in 10 CFR 50.36. The preface to this document encourages licensees to adopt some or all of the improved TS into

LGS Units 1&2: Relocation of Administrative Control Requirements Page 4 of 6 their existing TS. The TS sections proposed herein for relocation do not appear in the improved Standard Technical Specification (STS) presented in NUREG-1433, and accordingly, are not required to be in the TS.

Revisions to the administrative controls section of the LGS TS are currently subject to a no significance hazards consideration determination pursuant to 10 CFR 90.92. This, determination is oriented to design and operational requirements described in the TS. The administrative controls selected for relocation are considered by the NRC in the above referenced AL 95-06 to be quality assurance requirements, and therefore qualify for incorporation into documents describing the licensee's quality assurance program. As stated in AL 95-06, 10 CFR 50.54(a) is the appropriate regulation for controlling changes to these and other quality assurance program requirements. Prior NRC approval is required of any changes to the quality assurance program that reduce the commitments in the program description as accepted by the NRC. Accordingly, the proposed license amendment relocating these administrative requirements from the TS to a document subject to the controls of 10 CFR 50.54(a), results in an equivalent level of regulatory authority while providing for a more appropriate change control process.

5.0 REGULATORY ANIALYSIS 5.1 No Significant Hazards Consideration Exelon has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.90, "Issuance of amendment," as discussed below:

1.

Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No. The proposed changes involve the relocation of several administrative requirements from the Technical Specifications (TS) to a document subject to the control of 10 CFR 50.54(a), and is therefore, administrative in nature. The relocated requirements involve the onsite and offsite organization's review and audit, the review and approval of procedures, and the retention of records. The change will not alter the physical design or operational procedures associated with any plant structure, system, or component. The change does not reduce the duties and responsibilities of the organizations performing the review, audit, and approval functions essential to ensuring the safe operation of the plant.

Therefore, this proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.

2.

Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No. The proposed changes are administrative in nature. The changes do not alter the physical design, safety limits, or safety analysis assumptions, associated with the operation of the plant. Accordingly, the

LGS Units 1&2: Relocation of Administrative Control Requirements Page 5 of 6 changes do not introduce any new accident initiators, nor do they reduce or adversely affect the capabilities of any plant structure, system, or component to perform their safety function.

Therefore, the proposed amendment does not create the possibility of a new or different kind of accident from any previously evaluated.

3.

Does the proposed amendment involve a significant reduction in a margin of safety?

Response: No. The proposed changes conform to NRC regulatory guidance regarding the content of plant Technical Specifications. The guidance is presented in Administrative Letter 95-06, and NUREG-1433, Rev. 2. The relocation of these administrative requirements will not reduce the quality assurance commitments as accepted by the NRC, nor reduce administrative controls essential to the safe operation of the plant. Future changes to these administrative requirements will be performed in accordance with NRC regulation 10 CFR 50.54(a), consistent with the guidance identified above.

Accordingly, the relocation results in an equivalent level of regulatory control.

Therefore, the proposed change does not involve a significant reduction in a margin of safety.

Based on the above, Exelon concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of 'no significant hazards consideration" is justified.

5.2 Applicable Regulatory RequirementslCriteria The NRC provided guidance for the contents of TS in its "Final Policy Statement on Technical Specifications Improvement for Nuclear Power Reactors, 58 FR 39132, July 22, 1993. In particular, the NRC indicated that certain items could be relocated from the TS to licensee-controlled documents, and identified criteria to be used to determine the functions to be included in the Technical Specifications (TS). The NRC's policy statement provides that particular details of administrative controls may be relocated to licensee-controlled documents where section 50.54, 50.59, or other regulations provide adequate regulatory control. The NRC adopted revisions to 10 CFR 50.36, "Technical Specifications," pursuant to which the rule was revised to codify and incorporate these criteria. In adopting the revision of the rule, the NRC indicated that the intent of these criteria can be utilized to identify the optimum set of administrative controls in the TS. The NRC further concluded that the specific content of the administrative controls section of the TS is, therefore, that information which the Commission deems essential for the safe operation of the facility and which is not already adequately covered by other regulations. Accordingly, the NRC has determined that requirements that are not specifically required under 50.36(c)(5), and are not otherwise necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety, can be removed from TS administrative controls.

Consistent with this policy position, the NRC staff issued Administrative Letter (AL) 95-06, December 12, 1995, identifying TS administrative control requirements that qualify for relocation to licensee quality assurance control documents subject to the controls of 10 CFR

LGS Units 1&2: Relocation of Attachment I Administrative Control Requirements Page 6 of 6 50.54(a). Requirements identified by AL 95-06 included review and audit, procedure review and approval, and record retention requirements. The changes proposed herein conform to the NRC staff position presented in AL 95-06.

NRC approved NUREG-1433, "Standard Technical Specifications - General Electric Plants, BWR/4," Revision 2, identifies an improved TS that was developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvement for Nuclear Power Reactors, dated July 22, 1993, and subsequently codified in 10 CFR 50.36. The preface of this document encourages licensees to adopt some or all of the improved TS into their existing TS. The TS sections proposed herein for relocation do not appear in the improved Standard Technical Specification (STS) presented in NUREG-1433, and accordingly, are not required to be in the TS.

The proposed license amendment to relocate these administrative requirements to a document subject to the controls of 10 CFR 50.54(a), conforms with NRC guidance as stated above, and results in an equivalent level of regulatory control.

In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

6.0 ENVIRONMENTAL CONSIDERATION

The proposed amendment is confined to changes to administrative procedures or requirements. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(10). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.

I.

REFERENCES

1.

NRC "Final Policy Statement on Technical Specifications Improvement for Nuclear Power Reactors," (58 FR 39132, dated July 22, 1993).

2.

NRC Final Rule, 'Technical Specifications," 60 FR 36593 (July 19, 1995).

3.

10 CFR 50.36, "Technical Specifications."

4.

10 CFR 50.54, "Conditions of Licenses."

5.

10 CFR 50.92, "Issuance of Amendment."

6.

NRC Administrative Letter 95-06, "Relocation of Technical Specifications Administrative Controls Related to Quality Assurance."

7.

NUREG-1433, Revision 2, "Standard Technical Specifications-General Electric Plants.

BWR/4," June 2001.

ATTACHMENT 2 License Amendment Request Limerick Generating Station Units 1 and 2 Docket Nos. 50-352 and 50-353 Roloc-cte Administrative Control Requirements Maxrkipof Proposed Tprhnicrl Spr-rcificatinn Paoe (Chanpes Unit 1 TS Pages I Inif 9 TS Pnages xxvi xxvii 6-7 6-8 6-9 6-10 6-12 6-12a 6-13 6-19 6-20 6-21a 6-22 xxvi xxvii 6-7 6-8 6-9 6-10 6-12 6-12a 6-13 6-19 6-20 6-21a 6-22

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY.................................................. 6-1 6.2 ORGANIZATION................................................... 6-1 6.2.1 OFFSITE AND ONSITE ORGANIZATION

................... 6-1 Figure 6.2.1-1 Deleted.......

..................... 6-3 6.2.2 UNIT STAFF................................................... 6-2 Figure 6.2.2-1 Deleted.......

.................... 6-4 Table 6.2.2-1 Minimum Shift Crew Composition....................... 6-5 6.2.3 DELETED; Refer to note on page..........

........................ 6-6 6.2.4 SHIFT TECHNICAL ADVISOR...............

.......................... 6-6 6.3 UNIT STAFF QUALIFICATIONS 6-6 6.4 DELETED.........................

. 6-7 6.5 REVIEW AND AUDIT 6.5.1 2lant Operations Review, Committee (POQRC4 Vifd-e 4

-Pntineoc l%..P C.1124-t!.........

..... 6-7 WG.mpoGEi.n lk 1

t 6-7

-AI t.t-e-.

6-7

-Mceting Frequeney 6-7

.u.rum.-

6-7 Respensibiliticz D.e iX4 l.

6-8 L I U 1

xxvAmedmet..

.................................. 6-9 LIMERICK - UNIT I xxvi Amendment Noo., 3-5, 46, 4,E-G

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.5.2 NUCLEAR REVIEW -AG-ARD NRB). *Peklie4 jFunction i;,

AM 4Cpetin h................................

-Altenter, c.:

4... -............................

consutan-Re.fer-w.o.ot on pg..T.......

Reee-r 6.5.3 PROGRAMiPROGEDURi REVIEW ANDAPRVX el£i 6.6 REPORTABLE EVENT ACTION......................................

6.7 SAFETY LIMIT VIOLATION.......................................

6.8 PROCEDURES AND PROGRAMS......................................

6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPRS......................

Startup Repr e......................

Annual Re p

o r

t s

Monthly Operating Reports.*....

Annual Radiological Environmental Operating Report Semiannual Radioactive Effluent Release Reportt....

CORE OPERATING LIMITS RE.

O R

T S

6.9.2 SPECIAL REPORTS.

6.10....R......R....R.....N....Q...................................

6.11 RADIATION PROTECTION PROGRAM................................

6.12 HIGH RADIATION AREAd........................................

LIMERICK - UNIT a xxvii Amendment No.

a7, Report COE O 8 RPT 6-9 6-9 6-10 6-10 6-10 6-10 6-10 6-12 6-12 6-12a 6-12a 6-13 I

6-15 6-15 6-15 6-16 6-16 6-17 6-18a 6-18a 6-19 6-20 6-20

ADMIISTARAlI VE CONTROLS 6.4 DELETED 6.5 A4 AU!T TIDW I

e4 PERAT I S R VIEW CMMITTEE (P R F

TION 6.5.1. The PORC shall function to advise the Plant Manager on all matters related nuclear safety.

COMPOSITION 6.5.1.2 The Pla Operations Review Committee is composed of ni regular members from the Limerick Genera ing Station staff.

Members shall collecti ly have experience in th following areas:

Plant Operations Engineering Maintenance Instrumentation and Controls Planning Radiation Safety Chemistry Regulatory Assurance Members shall meet the requirements of SI/ANS X 1-1978, Section 4.7, for the applicable required experience and beappointed in riting by the Plant Manager.

The Chairman and alternate Chairme of the PORC shal be drawn from the PORC members and appointed in writing by the P ant Manager.

ALTERNATES 6.5.1.3 All alternate m ers shall be appointed in writing b the PORC Chairman to serve on a temporary asis; however, no more than two alterna s shall participate as votin embers in PORC activities at any one time.

MEETING FREQUEN CY/\\l 6.5.1.4 The RC shall meet at least once per calendar month and as cony ed by the PORC Chairm or his designated alternate.

QUORUM/

{

6.5..5 The quorum of the PORC necessary for the performance of the PORC res onsibility and authority provisions of these Technical Specifications shall c *sist of the Chairman or his designated alternate and four members including rnaCtes.

A/

T' e ) m 4O;4Ao&I Hte x5 It!'v

'(,*

5 4-he q A -i lees lae, VI4lo leW 4.v Amendment No. 1-0, 3X, 5, 945, 1-39, 4-60, 152-Correction Ltr dtd-10/17/95-LIMERICK - UNIT 1 6-7

ADMJ+/-II STRATIVLECONTROLS 5.1.6 The PORC shall be responsible for:

a. Review of (1) Administrative Procedures and changes thereto, (2) new programs or procedures required by specification 6.8 and requiring a 10 R

50.59 evaluation, and (3) proposed changes to programs or procedures quired by Specification 6.8 and requiring'a 10 CFR 50.59 evaluation

b. Rev w of all proposed tests and experiments that affect nuclear s ety;

c. Review f all proposed changes to Appendix A Technical Specific ions;

d. Review of 11 proposed changes or modifications to unit syst s or equipment that affect uclear safety;

e. DELETED.

f. Investigation of a violations of the Technical Spe fications, including the preparation and orwarding of reports covering valuation and recommendations to pr vent recurrence, to the Vic President, Limerick Generating Station, Plahf Manager, and to the Nu ear Review Board;

g. Review of all REPORTABLE E) NTS;

h. Review of unit operations to dtect poten al hazards to nuclear safety;

i. Performance of special reviews, i"tivesti ations, or analyses and reports thereon as requested by the Vice Pr~ dent, Limerick Generating Station, plant Manager or the Chairman of th clear Review Board;

j. Review of the Security Plan and pleme A ng procedures and submittal of recommended changes to the Nucl ar Review Board; and

k. Review of the Emergency Plan and implementing ocedures and submittal of the recommended changes to he Nuclear Review Bo rd.

1. Review of every unplann onsite release of radioac *ve material to the environs including the/preparation and forwarding of dports covering evaluation, recommen tions and disposition of the corrective action to prevent recurrence o the Vice President, Limerick Gener ting Station, Plan

Manager, and to t Nuclear Review Board.

m. Review of chan s to the PROCESS CONTROL PROGRAM, OFFSITE DO CALCULATION MANUAL, and r dwaste treatment systems.

n. Review of e Fire Protection Program and implementing procedure and the submitta of recommended changes to the Nuclear Review Board.

6.5.1.7 T

PORC shall:

a. Re mmend in writing to the Plant Manager approval or disapproval of items c nsidered under Specification 6.5.1.6a. through d. prior to their mplementation.

Render determinations in writing with regard to whether or not each item considered under Specification 6.5.1.6b. through f. requires NRC aproyal ursuant to CFR 505 Tlw1 CK-11 6-8 Amendment ijo. 4h0,Ao be be, 4elow441, Ac.

qL1 SiI CK U e7 T

m 6-8 Amendment No. 40, 4X, 4-4, ADS1, A4-S

ADMINISTRATIVE CONTROLS SONS BILITIES (ontinued--

c. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President, Limerick Generating Station and the Nuclear Review Board of disagree-ment between the PORC and the Plant Manager; however, the Plant Man-ager shall have responsibility for resolution of such disagreements ursuant to Specification 6.1.1.

RECORDS 6.5.1.8 The P C shall maintain written minutes of each PORC meeting that, at a minimum, doc ment the results of all PORC activities performed nder the responsibility pro isions of these Technical Specifications. Copi s shall be provided to the Vice President, Limerick Generating Station, Pla

Manager, and the nuclear Revie Board.

6.5.2 NUCLEAR REVIEW BO D (NRB)

FUNCTION 6.5.2.1 The NRB shall functi n to provide independet review and audit of designated activities in the ar s of:

a. Nuclear power plant oper tions,

b. Nuclear engineering,

c. Chemistry and radiochemistry,

d. Metallurgy,

e. Instrumentation and cont

f. Radiological safety,

9. Mechanical and ele rical engineering, an

h. Quality assuran practices.

The NRB shall report t and advise the Senior Vice Presi ent and Chief Nuclear Officer on those area of responsibility pertaining to N Review and Audits.

COMPOS IT ION 6.5.2.2 The Ch irnan, members; and alternates of the NRB sha be appointed in writing by 'fe Chief Nuclear Officer, and shall have an acadimic degree in an ngineering or physical science field; and in additi n, shall have a minimum of5 years technical experience, of which a minimum of \\ years shall be in one r more areas given in Specification 6.5.2.1. The NRB sh 11 be composed f no less than eight and no more than 12 members.

The me ers and alternates of the NRB will be competent in the area of Quality Assur nce practice and cognizant of the Quality Assurance requirements 10 CFR Par 50, Appendix B. Additionally, they will be cognizant of the corpor te Q

ity Assurance Program and will have the corporate Quality Assurance anization available to them.

Ti e-it, r-%,o ee4,A tz Je t v i

c PI 6 9

has YJ-et'ew NOV 1 6 a

-r ftve 0 ATHM Amendment No. 40,93, 96,434_

LIMERICK-UNJT 1 6-9

ADMTNTSTRATIVE CONTROLS

• TERNATES 6.5 -.3 All alternates shall be appointed in writing by the NRB Chairman to serve n a continuing basis.

They shall receive correspondence sent to URB members ith regard to NRB activities and shall be invited to attend all meetings.

Alternates shall vote only in the absence of those members f whom they are th alternate.

CONSULTANTS 6.5.2.4 Consult shall be utilized as determined b he NRB Chairman to provide expert advice tb the NRB.

MEETING FREQUENCY 6.5.2.5 The NRB shall meet a east once r calendar quarter during the initi; year of unit operation following funk loadi g and at least once per 6 months thereafter.

s II I

QOUORUM 6.5.2.6 The quorum of the 6R&necessary fo r he performance of the NRB rev and audit functions of these/Technical Specificatibnts shall consist of the Chairman or a designated alternate and at least four b t not less than one half of the voting NRB mbers.

No more than a minorit of the quorum shall have line responsibiX y for operation of the facility.

REVIEW 6.5.2.7 - DE 'ED.

The information from this section is located in he UFSAR.

AUDITS /

\\

6.5. 8 - DELETED.

The information from this section is located in the UFS iew 7
-w Th*e N OrVW4k&

40,11, A4 L -of eK ytlz.4,

-to -iie GA1-r LIMERICK -

UNIT I AUG 0 8 1995 6-10 Amendment No.

G-9

ADMINISTRATIVE CONTROLS 6.5..9 Records of NRB activities shall be prepared, approved, and distributed indic ed below:

a.

Minutes of each NRB meeting shall be prepared, approved, and orwarded to the Senior Vice President and Chief Nuclear Officer withi 4 days following ach e ting.

b.

Repor of Reviews shall be prepared, approved, an forwarded to the Senior e President and Chief Nuclear Officer thin 14 days.

following c etion of the review.

c.

Audit reports sh11 be forwarded to the Co orate Officer(s) and management positio responsible for the areas audited within 30 days after completio of the audit by e auditing organization.

6.5.3 PROGRAM/PROCEDURE REVIWAND VA All programs and procedures required by Sp ification 6.8 shall be reviewed and approved as described below.

6.5.3.1 Each new program, proce e, or chang thereto shall be independently reviewed by a Station Qualified Re ewer (SQR) who i knowledgeable in the functional area affected but is t the individual preparer.

The SQR may be from the same organization as the p eparer.

The SQR shall relher a determination in writing of whether or not cr ss-disciplinary review of a nhN program, procedure, or change thereto is neces ry.

If necessary, such review shall be performed by appropriate personnel.

6.5.3.2 Each ne program, procedure, or change thereto shall b reviewed by the Director or Manage designated by Administrative Procedures as the r ponsible Director or Mana r for that program or procedure, and the review shal include a determination H whether or not a 10 CFR 50.59 evaluation is required.

a 10 CFR 50.

evaluation is not required, the new program, procedure, or change th eto shall be approved by the responsible Director or Manager or te Plant Manager nor to implementation.

Administrative Procedures shall be reviewed y

PORC ior to approval. Administrative Procedures, Security Plan Implementing Pro dures, and Emergency Plan Implementing Procedures shall be approved by the nt Manager or his designated alternate in accordance with Specification 6.1.1.

1 ~ ~

~

~

~

4 he5rala 5Sc

.f 1.5 Stork MeID4ST/,4 s OkAT LIMERICK - UNIT I 6 -12 Amendment No. --0, -3, 4X, 46, +5-4

ADNJISIATIVE CJNROLL-5

.3.3 If the responsible Director or Manager determines at a new

gram, pro ure, or change thereto requires a 10 CFR 50.59 evaluation, the, ponsible Direct or Manager shall render a determination in writing of wh21fher or not the new

program, edure, or change thereto requires NRC approv 9ursuant to 10 CFR 50.59, and shall forw d the new program, procedure, or cha 5 thereto with the associated 10 CFR 50.59 eval ion to PORC for review.

If approval is required, obtain NRC approval prior to ementation of w program, procedure, or change.

6.5.3.4 Personnel recomme d

e SQRs shall be approved and designated as such by the PORC Chairman.

The re si Director or Manager shall ensure that a sufficient complement of S for their nctional area is maintained in accordance with Admini ative Procedures.

e SQRs shall meet or exceed the qualifications desc ed in Section 4.4 of ANSI 3.1-1978.

6Property "ANSI code" (as page type) with input value "ANSI 3.1-1978.</br></br>6" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..5.3.5 emporary procedure changes shall be reviewe approved in accordance with S ica ion 6.8.3.

6

.3.6 Records documenting the activities performed under Specifi s 6.5.3.1 hrough 6.5.3.5 shall be maintained in accordance with Specification 6.10.

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

a.

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

b.

Each REPORTABLE EVENT shall be reviewed by the PORC and submitted to the NRB, Plant Manager and the Vice President, Limerick Generating Station.

6,7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

The Vice President, Limerick Generating Station, Plant Manager, and the NRB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the NRB.

This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon unit components, systems, or structures, and (3) corrective action taken to prevent recurrence.

c.

The Safety Limit Violation Report shall be submitted to the Commission, the NRB, Plant Manager, and the Vice President, Limerick Generating Station, within the 14 days of the violation.

LIMERICK - UNIT 1 6-12a Amendment No. 4W, 96, 144

ADMINISTRATIVE CONTROLS SAFETY LIMET VIOLATION (Continued)

d.

Critical operation of the unit shall not be resumed until authorized by the Commission.

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.

The applicable procedures required to implement the requirements of NUREG-0737 and Supplement 1 to NUREG-0737.

c.

Refueling operations.

d.

Surveillance and test activities of safety-related equipment.

e.

Security Plan implementation.

f.

Emergency Plan implementation.

9.

Fire Protection Program implementation.

h.

PROCESS CONTROL PROGRAM implementation.

i.

OFFSITE DOSE CALCULATION MANUAL implementation.

j.

Quality Assurance Program for effluent and environmental monitoring, using the guidance of Regulatory Guide 4.15, February 1979.

Each procedure of Specification 6.8.1, and changes thereto, other proce or procedure change that the Plant Manager determines to a Mt nuclear safety, shajl be reviewed and approved in accordance with Sper.ifications 6.5.1.6, 6.5.1.7 and/or 6 5.3, as appropriate, prior to implementati-6.

Each procedure of Specification 6-S41 shall also be reviewed as set forty in Administrative Procedures.

6.8.3 Temporary changes to procedure* of Specification 6.8.1 may be made provided:

a.

The intent of the origihal procedure is not altered;

b.

The change is approved by two members of the unit management staff, at least one'_pf whom holds a Senior Operator license on the unit affected; and

c.,e change is documented, reviewed by an SQR in accordance with

/ Specification 6.5.3.1, and approved by either the Plant-Manager or his designated alternate in accordance with Specification 6.1.1>.-or the Director or Manager designated by Administrative Procedures as the--.responsible Director or Manager for that procedure within 14 days of implementat70n.,

Al A1AR 14 Z000 LIMERICK - UNIT 1 6-13 Amendment No.

dl d/ A' Goj.7 be t e )Vj17V-PRtA +) bet Wou k^~

t 6 -

ai Fresia relomW( to taxB'3 1-X(iWqt>X^,

H s.&s gIeese reloVA.W +DV r

ADMINISTRATIVE CONTROLS

6.

10 -RECORD RETEENTIO SPe-I-e4-6.10.1 In addition o the applicable record retention requirements of Title 10, de of Federal Regulations, the following records shall be retained for at least th minimum period indicated.

6.10.2 e following records shall be retained for at least 5 years:

a.

Recor and logs of unit operation covering time interval each power level.

b.

Records and ogs of principal maintenance activities inspections, repair, and re4 acement of principal items of equi ent related to nuclear safety.

c.

All REPORTABLE EVEN

d.

Records of surveillance tivities, insp tions, and calibrations required by these Technica Specificatp ns.

e.

Records of changes made to the ro0 ars and procedures required by Specification 6.8.

f.

Records of radioactive shipm s.

g.

Records of sealed source nd fission dete or leak tests and results.

h.

Records of annual ph ical inventory of all led source material of record.

6.10.3 The following r ords shall be retained for the dur ion of the unit Operating License:

a.

Records d drawing changes reflecting unit design modifi tions made to system and equipment described in the Final Safety Analysi Report.

b.

Re rds of new and irradiated fuel inventory, fuel transfers, a sembly burnup histories.

c.

Records of radiation exposure for all individuals entering radiation control areas.

to 4r e ( ATR.

LIMERICK -

UNIT 1 6-19 Amendment No.-4-7l JAN 0 2 1TM

ADMINISTRATIVE CONTROLS R

O (Cninued)/

/ d.\\ Records of gaseous and liquid radioactive material released toX I

~environs.

e.

R doftransient or operational cycles for thos nX mponents ident ied in Table 5.6.1-1.

f.

Records o eactor tests and experiments.

g.

Records of tra ing and qualification for cur'rent members of the unit staff.

I /

h.

Records of inservice spections perfo4md pursuant to these Technical Specifications.

i.

Records of quality assurance a ivities required by the Operational Quality Assurance Manual no ted in Section 6.10.2.

j.

Records of reviews perfo. ed for canges made to procedures or equip-ment or reviews of tests and experim ts pursuant to 10 CFR 50.59.

k.

Records of meeting /of the PORC and the 4.

1.

Records of th service lives of all snubbers ncluding the date at which the s vice life commences and associate installation and maintenayc'e records.

m.

Reco -

of analysis required by the Radiological Env onmental Mo toring Program that would permit evaluation of the ccuracy of e analysis at a later date.

n /

Records of reviews performed for changes made to the OFFSITE OSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

6.11 RADIATION PROTECTION PROGRAM 6.11.1 Procedures for personnel radiation protection shall be prepared con-sistent with the requirements of 10 CFR Part 20 and shall be approved, main-tained, and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601(a) and (b) of 10 CFR Part 20:

6.12.1 High Radiation Areas with dose rates (deep dose equivalent) greater than 0.1 rem/hr and not exceeding 1.0 rem/hour (at 30 centimeters from the radiation sources or from any surface penetrated by the radiation):

a.

Each accessible entryway to such an area shall be barricaded and conspicuously posted as a High Radiation Area.

Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.

2 2 1999 kwnd-ent N'o. -02, -Ft LIMERICK - UNIT I 6-20

ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued) a)

A health physics qualified individual (i.e.,

qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for controlling personnel radiation exposure within the area, OR b)

Be under the surveillance, as specified in the RWP or equivalent, by means of closed circuit television, of a health physics qualified individual (i.e., qualified in radiation protection procedures),

responsible for controlling personnel radiation exposure in the area, and with the means to communicate with the individuals in the area.

6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 Changes to the PCP:

• r I

) -vrw i ef t

rev >2to ax lrllo

'K ) }>h

&V trs

a.

Shall be documented

.ot~ior b

p~afjnt&asone O.4n. Thig docau-mnt-atin

1.

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and LIMERICK - UNIT 1 6-21a JUN 2 2 1999 ATP nctnt No. 4A&

ADMINISTRATIVE CONTROLS PROCESS CONTROL PROGRAM (Continued)

2.

A determination that the change did not reduce the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

b.

Shall become effective upon review and acceptance by the PORC and approval of the Plant Manager.

6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 Changes to the ODCM:

I 4

j l

4 A'--

v Ak + t -e o

416uw lkra*;Co

a.

Shall be documented, Mwtaned~s_;4fi; by aprfrtion 6 -In-3-- -Thi s-A-GUM Ftat i e

1.

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and

2.

A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b.

Shall become effective upon review and acceptance by the PORC and the approval of the Plant Manager.

c.

Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.

Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.

6.15 (Deleted) -

INFORMATION FROM THIS SECTION RELOCATED TO THE ODCM.

LIMERICK - UNIT 1 6-22 Anendment No6. 35, #L$, 73 AUir 10 '1

INDEX ADJ+/-I ISTRAVL N RS SECTION PAGE 6.1 RESPONSIBILITY................................................... 6-1 6.2 ORGANIZATION................................................... 6-1 6.2.1 OFFSITE AND ONSITE ORGANIZATION..............

................... 6-1 Figure 6.2.1-1 DELETED.......

.................... 6-3 6.2.2 UNIT STAFF................................................... 6-2 Figure 6.2.2-1 DELETED.......

.................... 6-4 Table 6.2.2-1 Minimum Shift Crew Composition....................... 6-5 6.2.3 DELETED; Refer to note on page.........

......................... 6-6 6.2.4 SHIFT TECHNICAL ADVISOR...............

.......................... 6-6 6.3 UNIT STAFF QUALIFICATIONS..................

...................... 6-6 6.4 DELETED........................

........................... 6-7 6.5 PREVIEW AND AUDIT p INec e 6.5.1 Plant 0pPPatiQPA Re'ipw Committee (PO¶-C

) CjpeI v4 eu.ctiM....:X 1

6-7 Comp4itin.712dd 6-7 Altenate-iteA-l.6-7 P

P.....................................

67 Meeting Frcuncig

.............................. 6-7 Q.or.m...:. (-.+.e....

6-7 Pecspon.ibilitic4

.6-8

- r-d s

-te(.......Y.

6-9 LIMERICK - UNIT 2 xxvi Amendment No. X, 60,

+2-2

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.5.2 NUGLEAR REV.'IEW BOARD (NR9p -P Function

.ThA...

6-9 e

.t

e.

6-9

-Alternatc.,.

6-10

-G0ei 5U 1 a R..... n t

A......................................

6-10 Mceting Frequency..........e.

6-10 Quorumn...Th. 1..

6-10 BfELETW-Rcfcr to note on pagio..X.'e 6-10

.R Gord..

.I?.C J dTef.................................

6-12 6.5.3

• PGRAMIPROCEDURE REV.'IEW AND APPRO':..A 6-12 6.6 REPORTABLE EVENT ACTION.6-12a 6.7 SAFETY LIMIT VIOLATION.6-12a 6.8 PROCEDURES AND PROGRAMS.6-13 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS...............................................

6-15 Startup Report................................................

6-15 Annual Reports................................................

6-15 Monthly Operating Reports.....................................

6-16 Annual Radiological Environmental Operating Report............

6-16 Semiannual Radioactive Effluent Release Report................

6-17 CORE OPERATING LIMITS REPORTS..................................

6-18a 6.9.2 SPECIAL REPORTS...............................................

6-18a 6.10 REORD RETENTION.

C.....

6-19 6.11 RADIATION PROTECTION PROGRAM.6-20 6.12 HIGH RADIATION AREA.6-20 LIMERICK - UNIT 2 xxvii Amendment No, 4, 4G.-

AUG O 8 1995

ADMINISTRATIVE CONTROLS 6.4 DELETED 6.5 RCVIEW D ANDI+- paiI

+ W4Iofe

.5.1.1 Th PORC shall function to advise the Plant Manager on all ma ers elated to n lear safety.

COMPOSITION

/

.5.1.2 The Plant O ations Review Committee is composed f nine regular embers from the LimericK Generating Station staff.

Memb rs shall collectively have experience in the fo wing areas:

Plant Operations Engineering Maintenance Instrumentation and Controls Planning Radiation Safety Chemistry Regulatory Assurance Members shall meet the requirements f ANSI/ANS 1-1978, Section 4.7, for the applicable required experience an e appointed in iriting by the Plant Manager.

The Chairman and alternate Chair en of the PORC sha lbe drawn from the PORC members and appointed in writing by th Plant Manager.

ALTERNATES 6.5.1.3 All alternate mbers shall be appointed in writing\\by the PORC Chairman to serve on a temporar basis; however, no more than two alternates shall participate as votin members in PORC activities at any one time>

MEETING FEUNC//H 6.5.1.4 The P C shall meet at least once per calendar month and as convened by the PORC Chairma or his designated alternate.

QUORUM

/

Q 6.-5.1. vThe quorum of the PORC necessary for the performance of the PORC respo0siility and authority provisions of these Technical Specifications shla~l/

con ft of the Chairman or his designated alternate and four members includin

-FD th~ e Q A -FT LIMERICK - UNIT 2 6-7 Amendment No.

2O, 6O, 4-02, 4-2-9, 424-

AnmINTSTPATTVF CONTROLS lu0ff0W ESPONSIBILITIES 6

1.6 The PORC shall be responsible for:

a. Review of (1) Administrative Procedures and changes thereto, (2) new p ograms or procedures required by Specification 6.8 and requiring 10 CFR 50.59 evaluation, and (3) proposed changes to programs or procedur s req red by' Specification 6.8 and requiring a 10 CFR 50.59 evalu ion;

b. Review f all proposed tests and experiments that affect.nuc17 r safety;

c. Review of 11 proposed. changes to Appendix A Technical Specifications;

d. Review of al proposed changes or modifications to unit ystems or equipment that affect n lear safety;

e. DELETED.

f.

Investigation of al violations of the Technical pecifications,' including the preparation and frwarding of reports covern evaluation and.

recommendations to prey t recurrence, to the VWce President, Limerick Generating Station, Plan Manager, and-to the uclear Review Board;

g. Review of all REPORTABLE EV TS;

h. Review of unit operations to dtect pote ial hazards to nuclear safety;

i. Performance of special reviews, est ations, or.analyses and reports thereon as requested by the Vice PDrdent, Limerick Generating Station, plant Manager or the Chairman of th e(uclear Review Board;

j. Review of the Security Plan and i plemehting procedures and submittal *of recommended changes to'the Nucle r Revie,1\\Board; and

k. Review of the Emergency Plan d implementing procedures and submittal of the recommended changes to t e Nuclear Review\\Board.

1. Review of every unplanned nsite release of radioactive material to the environs including the p Xparation and forwarding\\of reports covering evaluation, recommendat,1ons and disposition of the corrective action to prevent recurrence to he Vice President, Limerick Generating Station, Plant Manager, and to the uclear Review Board.

M. Review of changes, o the PROCESS CONTROL PROGRAM, OFFSITEDOSE CALCULATION MANUAL, and radwiste treatment systems.

n. Review of the ire Protection Program and implementing procedures and the submittal of/recommended changes to the Nuclear Review Board. a 6.5.1.7 The PORC shall:

a. Recommend in writing to the Plant Manager approval or disapproval oX items cons.i'dered under Specification 6.5.1.6a. through d. prior to their \\

implementation.

b. Render determinations in writing with regard to whether or not each item considered under Specification 6.5.1.6b. through f. requires NRC approval ant to 10 CFR 50.59.

LIMERICK - UNIT 2 6-8 Amendment No. 4L0, 68, 19, 4+i..

ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued)

c. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice Presid t, Limerick Generating Station and the Nuclear Review Board of di agree-ment between the PORC and the Plant Manager; however, the P1It Manager shall have responsibility for resolution of such d' agreements ursuant to Specification 6.1.1.

RECORDS 6.5.1.8 The PeRC shall maintain written minutes of each P0 meeting that, at a minimum, document the results of all PORC activities erformed under the responsibility pro isions of these Technical Specificati's. Copies shall be provided to the VicS President, Limerick Generating Sta ion, Plant Manager, and the Nuclear Revi Board.

6.5.2 NUCLEAR REVIEW B ARD (NRB)

FUNCTION 6.5.2.1 The NRB shall functi te to provide ind endent review and audit of designated activities in the a reas of:

a. Nuclear power plant operat ions,

b. Nuclear engineering,

\\

I

c. Chemistry and radiochemistry,

d. Metallurgy,

e. Instrumentation and cont ol,

f. Radiological safety,

g. Mechanical and ele rical engineering, and

h. Quality assuranc practices.

The NRB shall report t and advise the Senior Vice President. and Chief Nuclea on those areas of res onsibility pertaining to NRB Review and Audits.

COMPOSITION 6.5.2.2 The Ch rman, members, and alternates of the NRB shall be'A pointed in writing by e Chief Nuclear Officer, and shall have an academic degr e in an engineering or physical science field; and in adjtion, have a minimm of 5 years technical experience, of which a minimum of 3years shall be i one or more areas given in Specification 6.5.2.1. The NRB shall be compos d of no less than eight and no more than 12 members.

The me ers and alternates of the NRB will be competent in the area of Qual i Assurace practice and cognizant of the Quality Assurance requirements of 10t Part 0, Appendix B. Additionally, they will be cognizant of the corporate Qu ~ity Assurance Program and will have the corporate Quality Assurance anization available to them.

r Office shall I

-Ti' 14$OrWAbOV; 4#r&Wx i5er4ieA 4.5-hs 6etx rt/o404

-I-41e CiAM1K LIMERICK - UNIT 2 6-9 Amendment No. B. 60, NOV 1 6 1998

• ADMINISTRATIVE CONTROLS aTERNAT S -

6. 2.3 All alternates shall be appointed in writing by the NRB Chair n to serv on a continuing basis.

They shall receive correspondence sent t, RB member with regard to NRB activities and shall be invited to atten 11 NRB meetings. Alternates shall vote only in the absence of those mem rs for whom they are t alternate.

CONSULTANTS 6.5.2.4 Consul tts shall be utilized as determi by the NRB Chairman to provide expert advice the NRB.

MEETING FREQUENCY 6.5.2.5 The NRB shall meet least Ae per calendar quarter during the initial year of unit operation following oading and at least once per 6 months thereafter.

QUORUM 6.5.2.6 The quorum of t NRB necessary fo the performance of the NRB review and audit functions of t se Technical Specificat ns shall consist of the Chairman or a designat alternate and at least fou ut not less than one half of the voting N members.

No more than a minori of the quorum shall have line responsi ity for operation of the facility.

REVIEW 6.5.2.7 DELETED.

The information from this section is locate in the UFSAR.

6.2.8 DELETED.

The information from this section is located in th UFSAR.-

1-1e 1tLra"Ao

+0 -+k,- Q Aq-I 5 Jam-e64 )-Ij1pAI-e LIMERICK - UNIT 2 6-10 Amendment No.-&G-0 AUG 0 8 1im

ADM IN ISTRATIV EIQOERQLS R-6.5

.9 Records of NRB activities shall be prepared, approved, and distribute as indic ted below:

a.

Minutes of each NRB meeting shall be prepared, approved, an orwarded to the Senior Vice President and Chief Nuclear Officer withi 14 days following ac

b.

Repor of Reviews shall be prepared, approved, an orwarded to the Senior

• ce President and Chief Nuclear Officer hin 14 days following ompletion of the review.

c.

Audit reports all be forwarded to the Co orate Officer(s) and management posit ns responsible for the reas audited within 30 days after comp tion of the audit y the auditing organization.

6.5.3 PROGRAM/PROCEDURE REVIEW AN PROVAL/

All programs and procedures required by ification 6.8 shall be reviewed and approved as described below.

6.5.3.1 Each new program, proce e, or cha e thereto shall be independently reviewed by a Station Qualified Re ewer (SQR) whoAis knowledgeable in the functional area affected but is t the individual eparer. The SQR may be from the same organization as the pr parer. The SQR shall nder a determination in writing of whether or not cr s-disciplinary review of a ew program, procedure, or change thereto is necess ry.

If necessary, such review hall be performed by appropriate personnel.

6.5.3.2 Each new rogram, procedure, or change thereto shal e reviewed by the Director or Manage designated by Administrative Procedures as the t'esponsible Director or Managr for that program or procedure, and the review sh 1 include a determination whether or not a 10 CFR 50.59 evaluation is required. If a 10 CFR 50.

evaluation is not required, the new program, procedure, o change ther to shall be approved by the responsible Director or Manager or the Plant Manager ior to implementation. Administrative Procedures shall be review by PORC p or to approval. Administrative Procedures, Security Plan Implementin Proc ures, and Emergency Plan Implementing Procedures shall be approved by the 1 t Manager or his designated alternate in accordance with Specification 6.1.1.

Al--L k

A sk

-i- -th e

@k, LIMERICK - UNIT 2 6 -12 Amendment No. X, 4-0, 60, 1f8-

ADM INISTRATI VE CDANRQLS

3. If the responsible Director or Manager determines that a new program ocedur or cha thereto requires a 10 CFR 50.59 evaluation, the responsible D or o Manager s render a determination in writing of whether or not new program, procedure, or nge thereto requires NRC approval pursuant 0 CFR 50.59, and shall forward the new p g am, procedure, or change thereto w the associated 10 CFR 50.59 evaluation to PORC for view.

If NRC approval is uired, obtain NRC approval prior to implementation of the ne rogram, proced or change.

6.5.3.4 Personnel recommended to shall be approved and designated as such by the PORC Chairman. The responsibl ir or or Manager shall ensure that a sufficient complement of SQRs for their f tional are

• s maintained in accordance with Administrative Procedures.

e SQRs shall mee exceed the qualifications described in Section 4 of ANSI/ANS 3.1-1978.

6Property "ANSI code" (as page type) with input value "ANSI/ANS 3.1-1978.</br></br>6" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..5.3.5 Te rary procedure changes shall be reviewed d approved in accordance with Specif tion 6.8.3.

6.5.3 Records documenting the activities performed under Spec cations 6.5.3.1 thugh 6.5.3.5 shall be maintained in accordance with Specification 6.

6.6 REPORTABLE EVENT ACTION le 4vki 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a.

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

b.

Each REPORTABLE EVENT shall be reviewed by the PORC and submitted to the NRB, Plant Manager and the Vice President, Limerick Generating Station.

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The Vice President, Limerick Generating Station, Plant Manager, and the NRB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the NRB.

This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon unit components, systems, or structures, and (3) corrective action taken to prevent recurrence.

c.

The Safety Limit Violation Report shall be submitted to the Commission, the NRB, Plant Manager, and the Vice President, Limerick Generating Station, within the 14 days of the violation.

LIMERICK - UNIT 2 6-12a Amendment No. 4-0, 60, 4.14

ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION (Continued)

d.

Critical operation of the unit shall not be resumed until authorized by the Commission.

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.

The applicable procedures required to implement the requirements of NUREG-0737 and Supplement 1 to NUREG-0737.

c.

Refueling operations.

d.

Surveillance and test activities of safety-related equipment.

e.

Security Plan implementation.

f.

Emergency Plan implementation.

9.

Fire Protection Program implementation.

h.

PROCESS CONTROL PROGRAM implementation.

i.

OFFSITE DOSE CALCULATION MANUAL implementation.

j.

Quality Assurance Program for effluent and environmental monitorm using the guidance of Regulatory Guide 4.15, February 1979.

Each procedure of Specification 6.8.1, and changes thereto, and any other rocedure or procedure change that the Plant Manager determines to affect nuclear afety, shall be reviewed and approved in accordance with Specifications 6.5.1.6, 6.5.1.7 and/or 6.5.3, as appropriate, prior to implementation.

Each procedure of Spacification 6.8.1 shall also be reviewed as set forth in Administrative Procedures.

6.8.3 Temporary changes to procedures of Specification 6.8.1 may be made rovided:

a.

The intent of the original procedure is not altered;

b.

The change is approved by two members of the unit management staff, at least one of whom holds a Senior Operator license on the unit affected; and

c.

The change is documented, reviewed by an SQR in accordance with Specification 6.5.3.1, and approved by either the Plant Manager or his designated alternate in accordance with Specification 6.1.1, or the Director or Manager designated by Administrative Procedures as the responsibl

_er for tat procedure within 14 days of implementation.

L R -

U 2r t tr trou 5 e 6-1 3

Amenetdment 4

o.

fhye VA-4 LIMERICK - UNIT 2 6-13 Amendment No. 70, 6,tE

ADMINISTRATIVE CONTROLS 6.10 *RECORD RETENTIO4II t? e

~e t6.'0.1 I n adiin-oteapial eodrtnin requirements of Title 10, CodN!of Federal Regulations, the following records shall be retained for at 1 ast the m i mum period indicated./

I 6.10.2 The ollowing records shall be retained for at least 5 years:

a.

Records d logs of unit operation covering time interv at each power level.

b.

Records and lo of principal maintenance activiV s, inspections, repair, and repl ement of principal items of eq ipment related to nuclear safety.

c.

All REPORTABLE EVENTS.

d.

Records of surveillance ac ' vities, inspections, and calibrations required by these Technical Secifications.

e.

Records of changes made to the o rans and procedures required by Specification 6.8.

f.

Records of radioactive shipments.

a.

Records of sealed source and fission de r leak tests and results.

h.

Records of annual hysical inventory of all ed source material of record.

6.10.3 The followin records shall be retained for the durat on of the unit Operating License:

a.

Recor and drawing changes reflecting unit design modific tions made to sys ms and equipment described in the Final Safety Analysiso eport.

b.

ecords of new and irradiated fuel inventory, fuel transfers, an

/ ssembly burnup histories.\\

/c.

Rcord of adiation exposure for all individuals entering radiation 1k*

IhtOrueA41O&4 b rav 5e tmn i' G ha. be-e$ re

-to,( +o L RC 6~/V--rpU LIMERICK -

UNIT 2 6-19 Amendment No~-+/-f-JAE 02 IS3

ADMINISTRATIVE CONTROLS Fr6PD RTENION(Continued)

Records of gaseous and liquid radioactive material released t

\\ nvirons./I

e.

Xcords of transient or operational cycles for those uni X mponents ideh ' fled in Table 5.6.1-1./

f.

Records f reactor tests and experiments.

g.

Records of raining and qualification for curret members of the unit staff.

h.

Records of inservicesinspections perfo d pursuant to these Technical Specifications.

i.

Records of quality assurance act ities required by the Operational Quality Assurance Manual noN sted in Section 6.10.2.

j.

Records of reviews perfo d fo tanges made to procedures or equip-ment or revi~ews of test and experi ejts pursuant to 10 CFR 50.59.

k.

Records of meeting the PORC and the iRB.

1.

Records of the ervice lives of all snubbers including the date at which the se ice life commences and associateckinstallation and maintenanc records.

m.

Recor of analysis required by the Radiological Environmental MoWtoring Program that would permit evaluation of the Eccuracy of e analysis at a later date.

n./

Records of reviews performed for changes made to the OFFSITE\\QSE

< ra~r:T~oN ANUAL and the PROCESS CONTROL PROGRAM.

6.11 RADIATION PROTECTION PROGRAM 6.11.1 Procedures for personnel radiation protection shall be prepared con-sistent with the requirements of 10 CFR Part 20 and shall be approved, main-tained, and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601(a) and (b) of 10 CFR Part 20:

6.12.1 High Radiation Areas with dose rates (deep dose equivalent) greater than 0.1 rem/hr and not exceeding 1.0 rem/hour (at 30 centimeters from the radiation sources or from any surface penetrated by the radiation):

a.

Each accessible entryway to such an area shall be barricaded and conspicuously posted as a High Radiation Area.

Such barricades may be opened as necessary to permit entry or 22 exit of personnel or equipment.

JUN 2 2 19 ATandcrnt Ib.

14. -+PP-LIMERICK - UNIT 2 6-20

ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued) a)

A health physics qualified individual (i.e.,

qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for controlling personnel radiation exposure within the area, OR b)

Be under the surveillance, as specified in the RWP or equivalent, by means of closed circuit television, of a health physics qualified individual (i.e., qualified in radiation protection procedures),

responsible for controlling personnel radiation exposure in the area, and with the means to communicate with the individuals in the area.

6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 Changes to the PCP:

a_

th

a.

Shall be documenteda rccords of rev.'is' 1 p

g sl

=ohn11 hb

-ratained-as-xreqW-r- ~b-peci-f~c-ation-6,}0,3n-_-;4-d i-do((entat>ef Fohali anta

1.

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and JUN 2 2 1N9 LIMERICK - UNIT 2 6-21a Aremttent Nb.

4 ADMINTSTRATIVE CONTROLS PROCESS CONTROL PROGRAM (Continued)

2.

A determination that the change did not reduce the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

b.

Shall become effective upon review and acceptance by the PORC and approval of the Plant Manager.

6.14 OFFSITE DOSE CALCULATION MANUAL (00CM) 6.14.1 Changes to the ODCM:

a.

Shall be documented record-s f

-eLe4b-

1.

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and

2.

A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b.

Shall become effective upon review and acceptance by the PORC and the approval of the Plant Manager.

c.

Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.

Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.

6.15 (Deleted) -

INFORMATION FROM THIS SECTION RELOCATED TO THE 00CM.

LIMERICK - UNIT 2 6-22 Amendment No. 7, ;, SE-AUG 10 2

ATTACHMENT 3 License Amendment Request Limerick Generating Station Units 1 and 2 Docket Nos. 50-352 and 50-353 Relocate Administrative Control Requirements Typed Ter~hnical Spacific2tinn Paige Chqnges Ijnif ITS Pages xxvi xxvii 6-7 6-8 6-9 6-10 6-12 6-12a 6-13 6-19 6-20 6-21a 6-22 I Init 9 TS Pages xxvi xxvii 6-7 6-8 6-9 6-10 6-12 6-12a 6-13 6-19 6-20 6-21a 6-22

INDEX ADMINISISRATI VECONTROLS

.=

-G.

SECTION PAGE 6.1 RESPONSIBILITY................................................... 6-1 6.2 ORGANIZATION.................................................... 6-1 6.2.1 OFFSITE AND ONSITE ORGANIZATION

................................. 6-1 Figure 6.2.1-1 Deleted

................ 6-3 6.2.2 UNIT STAFF.................................................... 6-2 Figure 6.2.2-1 Deleted

................ 6-4 Table 6.2.2-1 Minimum Shift Crew Composition....................... 6-5 6.2.3 DELETED; Refer to note on page.........

......................... 6-6 6.2.4 SHIFT TECHNICAL ADVISOR..............

........................... 6-6 6.3 UNIT STAFF QUALIFICATIONS........................................ 6-6 6.4 DELETED.................................................... 6-7 6.5 DELETED 6.5.1 Deleted Deleted................................................... 6-7 Deleted................................................... 6-7 Deleted................................................... 6-7 Deleted................................................... 6-7 Deleted................................................... 6-7 Deleted................................................... 6-8 Deleted................................................... 6-9 I

LIMERICK - UNIT I xxv1 Amendment No. -33, -35, 96, 1-60.

INDEX ADIILNISTRAIVLYLCONIRO LS SECTION PAGE 6.5.2 Deleted Deleted.................................................... 6-9 Deleted.................................................... 6-9 Deleted.................................................... 6-10 l

Deleted.................................................... 6-10 l

Deleted.................................................... 6-10 l

Deleted.................................................... 6-10 l

Deleted.................................................... 6-10 l

Deleted.................................................... 6-12 l

6.5.3 Deleted.6-12 6.6 REPORTABLE EVENT ACTION.........

...................... 6-12a 6.7 SAFETY LIMIT VIOLATION

................ 6-12a 6.8 PROCEDURES AND PROGRAMS

................ 6-13 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS............................................ 6-15 Startup Report.6-15 Annual Reports.6-15 Monthly Operating Reports.6-16 Annual Radiological Environmental Operating Report.6-16 Semiannual Radioactive Effluent Release Report.6-17 CORE OPERATING LIMITS REPORTS.6-18a 6.9.2 SPECIAL REPORTS............................................ 6-18a 6.10 DELETED...............................

6-19 l 6.11 RADIATION PROTECTION PROGRAM.

............................... 6-20 6.12 HIGH RADIATION AREA............................... 6-20 LIMERICK - UNIT 1 xxvi i Amendment No.

13, A7, 46,

ADMINISTRATIVE...CONTROLS..

6.4 DELETED 6.5 DELETED THE INFORMATION FROM SECTION 6.5 HAS BEEN RELOCATED TO THE OATR LIMERICK - UNIT 1 6-7 Amendment No. -0, -33, fi5, -6, 4-39,

-160. -16, rorec-t-iG n-Itrp---d td 4-47/-9 5

AQMIN1STRA V-L-COIROL$ _____LS._

THE INFORMATION FROM SECTION 6.5 HAS BEEN RELOCATED TO THE QATR LIMERICK - UNIT I 6 -8 Amendment No. -10, 4-7, 4-14, 43-1, 4-54,

ADjMIRTBATI VLCEOUCONlTROLS THE INFORMATION FROM SECTION 6.5 HAS BEEN RELOCATED TO THE QATR LIMERICK - UNIT I 6-9 Amendment No. 40, 5, 96, 1-34,

ADM-lNMIJT AlCOVE-COTRSROS THE INFORMATION FROM SECTION 6.5 HAS BEEN RELOCATED TO THE QATR LIMERICK - UNIT 1 65-10 Amendment No. -96,

TD LFR ORSLRAETVN CJ HTBEORLS

=__ATE THE THE INFORMATION FROMW SECTION 6.5 HAS BEEN RELOCATED TO THE QATR LIMERICK - UNIT 1 6-12 Amendment No. -40, 35, 4-7, -96, 4-54,

i Tf hIRES NIIRO.S_=______====

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

a.

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

b.

Each REPORTABLE EVENT shall be reviewed by the PORC and submitted to the NRB, Plant Manager and the Vice President, Limerick Generating Station.

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

The Vice President, Limerick Generating Station, Plant Manager, and the NRB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the NRB.

This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon unit components, systems, or structures, and (3) corrective action taken to prevent recurrence.

c.

The Safety Limit Violation Report shall be submitted to the Commission, the NRB, Plant Manager, and the Vice President, Limerick Generating Station, within the 14 days of the violation.

LIMERICK - UNIT I 6 -12a Amendment No. 4X, i, 4-54,

ADQMN ISTRATTECONTROLS.= =

=_

SAFETY LIMIT VIOLATION (Continued)

d.

Critical operation of the unit shall not be resumed until authorized by the Commission.

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.

The applicable procedures required to implement the requirements of NUREG-0737 and Supplement 1 to NUREG-0737.

c.

Refueling operations.

d.

Surveillance and test activities of safety-related equipment.

e.

Security Plan implementation.

f.

Emergency Plan implementation.

g.

Fire Protection Program implementation.

h.

PROCESS CONTROL PROGRAM implementation.

i.

OFFSITE DOSE CALCULATION MANUAL implementation.

j.

Quality Assurance Program for effluent and environmental monitoring, using the guidance of Regulatory Guide 4.15, February 1979.

6.8.2 The information from Section 6.8.2 has been relocated to QATR.

6.8.3 The information from Section 6.8.3 has been relocated to QATR.

LIMERICK - UNIT 1 6 -13 Amendment No. 40, 4X, 96, 4-39,

ADMIN LSIRAI VELCONT-ROLS

=_

6.10 DELETED THE INFORMATION FROM SECTION 6.10 HAS BEEN RELOCATED TO THE QATR.

LIMERICK - UNIT 1 6 -19 Amendment No. 4-7,

ADHTNISIRATHVELJUNTrROLS --

=

6.11 RADIATION PROTECTION PROGRAM 6.11.1 Procedures for personnel radiation protection shall be prepared con-sistent with the requirements of 10 CFR Part 20 and shall be approved, main-tained, and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601(a) and (b) of 10 CFR Part 20:

6.12.1 High Radiation Areas with dose rates (deep dose equivalent) greater than 0.1 rem/hr and not exceeding 1.0 rem/hour (at 30 centimeters from the radiation sources or from any surface penetrated by the radiation):

a.

Each accessible entryway to such an area shall be barricaded and conspicuously posted as a High Radiation Area.

Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.

LIMIERICK - UNIT I 6 -20 Amendment No. 48, 43-5,

ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued) a)

A health physics qualified individual (i.e.,

qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for controlling personnel radiation exposure within the area, OR b)

Be under the surveillance, as specified in the RWP or equivalent, by means of closed circuit television, of a health physics qualified individual (i.e., qualified in radiation protection procedures),

responsible for controlling personnel radiation exposure in the area, and with the means to communicate with the individuals in the area.

6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 Changes to the PCP:

a.

Shall be documented with the following information:

1.

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and LIMERICK - UNIT 1 6-21a Amendment No. 1-3-5,

ADMINISTRATIVE CONTROLS PROCESS CONTROL PROGRAM (Continued)

2.

A determination that the change did not reduce the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

b.

Shall become effective upon review and acceptance by the PORC and approval of the Plant Manager.

6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 Changes to the ODCM:

a.

Shall be documented with the following information:

1.

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and

2.

A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b.

Shall become effective upon review and acceptance by the PORC and the approval of the Plant Manager.

c.

Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.

6.15 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE ODCM.

LIMERICK - UNIT 1 6 -22 Amendment No. 35, 48, -73,

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY................................................. 6-1 6.2 ORGANIZATION................................................. 6-1 6.2.1 OFFSITE AND ONSITE ORGANIZATION..........

....................... 6-1 Figure 6.2.1-1 DELETED........................... 6-3 6.2.2 UNIT STAFF................................................. 6-2 Figure 6.2.2-1 DELETED........................... 6-4 Table 6.2.2-1 Minimum Shift Crew Composition....................... 6-5 6.2.3 DELETED; Refer to note on page

................... 6-6 6.2.4 SHIFT TECHNICAL ADVISOR......................................... 6-6 6.3 UNIT STAFF QUALIFICATIONS................

........................ 6-6 6.4 DELETED.

................................................. 6-7 6.5 DELETED 6.5.1 Deleted I

I Deleted...................................................

Deleted...................................................

Deleted...................................................

Deleted...................................................

Deleted...................................................

Deleted...................................................

Deleted...................................................

6-7 6-7 6-7 6-7 6-7 6-8 6-9 I

I I

I I

I I

I LIMERICK - UNIT 2 xxvi Amendment No. X, &O, 4-2k,

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.5.2 Deleted Deleted................................................... 6-9.

Deleted................................................... 6-9 Deleted................................................... 6-10 Deleted................................................... 6-10 Deleted................................................... 6-10 Deleted................................................... 6-10 Deleted................................................... 6-10 Deleted................................................... 6-12 6.5.3 Deleted.6-12 6.6 REPORTABLE EVENT ACTION.........................

6-12a 6.7 SAFETY LIMIT VIOLATION.........................

6-12a 6.8 PROCEDURES AND PROGRAMS.........................

6-13 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS 6-15 Startup Report.6-15 Annual Reports...........

6-15 Monthly Operating Reports................................. 6-16 Annual Radiological Environmental Operating Report........ 6-16 Semiannual Radioactive Effluent Release Report............ 6-17 CORE OPERATING LIMITS REPORTS............................. 6-18a 6.9.2 SPECIAL REPORTS........................................... 6 -18a 6.10 DELETED...............................

6-19 6.11 RADIATION PROTECTION PROGRAM................................

6-20 6.12 HIGH RADIATION AREA............................... 6-20 LIMERICK - UNIT 2 xxvi i Amendment No. 4, 60,

ADMINISTRATIVE CONTROLS 6.4 DELETED 6.5 DELETED THE INFORMATION FROM SECTION 6.5 HAS BEEN RELOCATED TO THE QATR LIMERICK - UNIT 2 6-7 Amendment No. 20, 60, 402-, 1-292, 4-24,

ADMINISTRATIVE CONTROLS THE INFORMATION FROM SECTION 6.5 HAS BEEN RELOCATED TO THE QATR LIMERICK - UNIT 2 6-8 Amendment No. 40, 68, 92, 448,

ADMINISTRATIVE CONTROLS THE INFORMATION FROM SECTION 6.5 HAS BEEN RELOCATED TO THE QATR LIMERICK - UNIT 2 6 -9 Amendment No. X, 60, 94,

ADMINISTRATIVE CONTROLS THE INFORMATION FROM SECTION 6.5 HAS BEEN RELOCATED TO THE QATR LIMERICK - UNIT 2 6-10 Amendment No. &Q,

ADMINISTRATIVE CONTROLS THE INFORMATION FROM SECTION 6.5 HAS BEEN RELOCATED TO THE QATR LIMERICK - UNIT 2 6-12 Amendment No. X, 40, 60, 448,

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 a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and

b.

Each REPORTABLE EVENT shall be reviewed by the PORC and submitted to the NRB, Plant Manager and the Vice President, Limerick Generating Station.

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a.

The NRC Operations Center shall and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Station, Plant Manager, and the be notified by telephone as soon as possible The Vice President, Limerick Generating NRB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the NRB.

This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon unit components, systems, or structures, and (3) corrective action taken to prevent recurrence.

c.

The Safety Limit Violation Report shall be submitted NRB, Plant Manager, and the Vice President, Limerick within the 14 days of the violation.

to the Commission, the Generating Station, LIMERICK - UNIT 2 6-12a Amendment No..-0, &0, 4--8,

ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION (Continued)

d.

Critical operation of the unit shall not be resumed until authorized by the Commission.

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.

The applicable procedures required to implement the requirements of NUREG-0737 and Supplement 1 to NUREG-0737.

c.

Refueling operations.

d.

Surveillance and test activities of safety-related equipment.

e.

Security Plan implementation.

f.

Emergency Plan implementation.

9.

Fire Protection Program implementation.

h.

PROCESS CONTROL PROGRAM implementation.

i.

OFFSITE DOSE CALCULATION MANUAL implementation.

j.

Quality Assurance Program for effluent and environmental monitoring, using the guidance of Regulatory Guide 4.15, February 1979.

6.8.2 The information from Section 6.8.2 has been relocated to the QATR.

6.8.3 The information from Section 6.8.3 has been relocated to the QATR.

LIMERICK - UNIT 2 6-13 Amendment No. -0, 60, 402,

ADMINISTRATIVE CONTROLS 6.10 DELETED THE INFORMATION FROM SECTION 6.10 HAS BEEN RELOCATED TO THE QATR LIMERICK - UNIT 2 6-19 Amendment No. 4As,

ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM 6.11.1 Procedures for personnel radiation protection shall be prepared con-sistent with the requirements of 10 CFR Part 20 and shall be approved, main-tained, and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601(a) and Cb) of 10 CFR Part 20:

6.12.1 High Radiation Areas with dose rates (deep dose equivalent) greater than 0.1 rem/hr and not exceeding 1.0 rem/hour (at 30 centimeters from the radiation sources or from any surface penetrated by the radiation):

a.

Each accessible entryway to such an area shall be barricaded and conspicuously posted as a High Radiation Area.

Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.

LIMERICK - UNIT 2 6 -20 Amendment No. 44, 400,

ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued) a)

A health physics qualified individual (i.e.,

qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for controlling personnel radiation exposure within the area, OR b)

Be under the surveillance, as specified in the RWP or equivalent, by means of closed circuit television, of a health physics qualified individual (i.e., qualified in radiation protection procedures),

responsible for controlling personnel radiation exposure in the area, and with the means to communicate with the individuals in the area.

6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 Changes to the PCP:

a.

Shall be documented with the following information:

1.

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and LIMERICK - UNIT 2 6-21a Amendment No. 4-At,

ADMINISTRATIVE CONTROLS PROCESS CONTROL PROGRAM (Continued)

2.

A determination that the change did not reduce the overall

.conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

b.

Shall become effective upon review and acceptance by the PORC and approval of the Plant Manager.

6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 Changes to the ODCM:

a.

Shall be documented with the following information:

1.

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and

2.

A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b.

Shall become effective upon review and acceptance by the PORC and the approval of the Plant Manager.

c.

Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.

Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.

6.15 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE ODCM.

LIMERICK - UNIT 2 6-22 Amendment No. X, 14,

-3,