Text

License Amendment Request - Revision of Salem and Hope Creek Generating Station Technical Specification (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS
	ML21272A184
Person / Time
Site:	Salem, Hope Creek
Issue date:	09/29/2021
From:	Mannai D; Public Service Enterprise Group
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	LAR H21-06, LAR S21-04, LR-N21-0065
	Download: ML21272A184 (56)
	v • d • e

10 CFR 50.90 LR-N21-0065 LAR S21-04 LAR H21-06 September 29, 2021 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Salem Generating Station Units 1 and 2 Renewed Facility Operating License Nos. DPR-70 and DPR-75 NRC Docket Nos. 50-272 and 50-311 Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 NRC Docket No. 50-354

Subject:

License Amendment Request - Revision of Salem and Hope Creek Generating Station Technical Specification (TS) to Delete Definitions found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS In accordance with 10 CFR 50.90, PSEG Nuclear LLC (PSEG) hereby requests amendments to Renewed Facility Operating License (FOL) Nos. DPR-70 and DPR-75 for Salem Generating Station Units 1 & 2 (Salem) respectively and FOL No. NPF-57 for Hope Creek Generating Station (Hope Creek). In accordance with 10 CFR 50.91(b)(1), a copy of this request for amendment has been sent to the State of New Jersey.

The proposed amendment revises the TS for the above plants to remove TS definitions for Member(s) of the Public, Site Boundary, and Unrestricted Area which are already present in the definitions found in the Offsite Dose Calculation Manual for each site as well as 10 CFR 20.1003. References to these definitions within the Salem and Hope Creek TS are also proposed to be revised to identify that they are no longer formal TS Definitions. The proposed amendment also removes figures of the site and surrounding area from the TS for the above plants. The proposed changes eliminate uncertainty in defining controlled areas within the site boundary to which access can be limited by PSEG for any reason, including for purposes of protection of individuals including members of the public from exposure to radiation and radioactive materials in effluents, as required by the TS and regulations.

The enclosure to this letter provides a detailed description and evaluation of the proposed changes.

LR-N21-0065 10 CFR 50.90 Page 2 Attachments 1 and 2 provide markups of the proposed changes to the affected pages of the TS for Salem Unit 1 and Salem Unit 2 respectively. provides a markup of the proposed changes to the affected pages of the TS for Hope Creek. provides a markup of the proposed changes to the TS Bases for Salem Units 1 and 2 for information. provides a markup of the proposed changes to the TS Bases for Hope Creek for information.

PSEG considers the proposed changes to be administrative in nature and therefore requests approval of this LAR within six months of NRC acceptance. Once approved, the amendment will be implemented within 60 days from the date of issuance.

There are no regulatory commitments contained in this letter.

If there are any questions or if additional information is needed, please contact Mr. Michael Wiwel at 856-339-7907.

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

Executed on ___September 29, 2021__

(Date)

Respectfully, Mannai, Digitally signed by Mannai, David David Date: 2021.09.29 10:49:16 -04'00' David Mannai Senior Director - Regulatory Affairs and Nuclear Oversight PSEG Nuclear

Enclosure:

Description and Evaluation of the Proposed Change : Mark-up of the Current Salem Generating Station Unit 1 TS Pages : Mark-up of the Current Salem Generating Station Unit 2 TS Pages : Mark-up of the Current Hope Creek Generating Station TS Pages : Mark-up of the Current Salem Generating Station TS Bases pages for information : Mark-up of the Current Hope Creek Generating Station TS Bases pages for information cc: Administrator, Region I, NRC Mr. J. Kim, NRC Project Manager, Salem & Hope Creek NRC Senior Resident Inspector, Salem NRC Senior Resident Inspector, Hope Creek Ms. Ann Pfaff, Manager NJBNE

LR-N21-0065 LAR S21-04 LAR H21-06 Enclosure Description and Evaluation of the Proposed Change License Amendment Request - Revision of Salem and Hope Creek Generating Station Technical Specification (TS) to Delete Definitions found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS Table of Contents 1.0

SUMMARY

DESCRIPTION.2 2.0 DETAILED DESCRIPTION ............................................................................................... 2 2.1 Salem TS DEFINITIONS to be Deleted ..................................................................... 2 2.2 Salem TS Figures to be Deleted ................................................................................ 3 2.3 Salem TS Impacted by Deletion of DEFINTIONS and Figures .................................. 3 2.4 Hope Creek TS DEFINITIONS to be Deleted ............................................................ 3 2.5 Hope Creek TS Figures to be Deleted4 2.6 Hope Creek TS Impacted by Deletion of DEFINITIONS and Figures...4 2.7 Reason for the Proposed Change...4 2.8 Description of the Proposed Change..5

3.0 TECHNICAL EVALUATION

.............................................................................................. 5

4.0 REGULATORY EVALUATION

.......................................................................................... 6 4.1 Applicable Regulatory Requirements/Criteria ............................................................ 6 4.2 Precedents ................................................................................................................. 6 4.3 No Significant Hazards Consideration Analysis ......................................................... 7 4.4 Conclusion ................................................................................................................. 8

5.0 ENVIRONMENTAL CONSIDERATION

............................................................................ 9

6.0 REFERENCES

.................................................................................................................. 9 ATTACHMENTS:

1. Mark-up of the Current Salem Generating Station Unit 1 TS Pages

2. Mark-up of the Current Salem Generating Station Unit 2 TS Pages

3. Mark-up of the Current Hope Creek Generating Station TS Pages

4. Mark-up of the Current Salem Generating Station Units 1 and 2 TS Bases Pages for information

5. Mark-up of the Current Hope Creek Generating Station TS Bases Pages for information 1 of 9

LR-N21-0065 LAR S21-04 LAR H21-06 1.0

SUMMARY

DESCRIPTION This license amendment request proposes to revise Section 1.0 in both the Salem Generating Station (Salem) and Hope Creek Generating Station (Hope Creek) Technical Specifications (TS) to delete the DEFINITIONS for MEMBER(S) OF THE PUBLIC, SITE BOUNDARY, and UNRESTRICTED AREA. These terms are already defined in the Offsite Dose Calculation Manuals (ODCM) for both stations and as well as in the definitions contained in 10 CFR 20.1003. In conjunction with these changes, references to these deleted DEFINITIONS within Salem and Hope Creek TS are proposed to be revised to show them in non-capitalized font to reflect that they are no longer TS DEFINITIONS. This change is consistent with the DEFINITIONS contained in NUREG-1431, Standard Technical Specifications - Westinghouse Plants and NUREG-1433, Standard Technical Specifications - General Electric Plants (BWR/4).

The proposed change also removes figures portraying the Plant Site, Exclusion Area and Low Population Zone from TS Section 5 from both Salem and Hope Creek TS. TS Section 5.1 of both stations is proposed to be revised to provide a text description of the location of the plant due to the proposed removal of the site figures currently referenced in this section.

2.0 DETAILED DESCRIPTION The Salem and Hope Creek TS proposed to be deleted or revised are identified below.

2.1 Salem TS DEFINITIONS to be Deleted MEMBER(S) OF THE PUBLIC 1.16 MEMBER(S) OF THE PUBLIC shall be all those persons who are not occupationally associated with the plant. This category does not include employees of PSE&G, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

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 UNRESTRICTED AREA 1.35 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY, access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or industrial, commercial, institutional, and/or recreational purposes.

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LR-N21-0065 LAR S21-04 LAR H21-06 2.2 Salem TS Figures to be Deleted Figure 5.1 Exclusion Area - See TS Page 5-2 of Attachments 1 and 2 Figure 5.1 Low Population Zone - See TS Page 5-3 of Attachments 1 and 2 Figure 5.1 Area Plot Plan of Site - See TS page 5-3a of Attachments 1 and 2 2.3 Salem TS Impacted by Deletion of DEFINITIONS and Figures TS INDEX to remove deleted DEFINITIONS TS 5.1.1 EXCLUSION AREA - Deleted and replaced with new Section 5.1 SITE LOCATION.

TS 5.1.2 LOW POPULATION ZONE - Deleted and replaced with new Section 5.1 SITE LOCATION TS 5.1.3 UNRESTRICTED AREAS FOR RADIOACTIVE GASESOUS AND LIQUID EFFLUENTS - Deleted and replaced with new Section 5.1 SITE LOCATION New TS Section 5.1 added to replace TS 5.1.1, 5.1.2 and 5.1.3:

5.1 SITE LOCATION Salem Generating Station is located in Salem County, New Jersey along the eastern shore of the Delaware River approximately 8 miles southwest of Salem, New Jersey and 18 miles south of Wilmington, Delaware.

TS Section 6.8.4.g - Radioactive Effluent Controls Program - Replace capitalized font for the terms MEMBERS OF THE PUBLIC, UNRESTRICTED AREA and SITE BOUNDARY that are referenced within TS 6.8.4.g with normal (non-capitalized) font to reflect their deletion from TS DEFINITIONS.

2.4 Hope Creek TS DEFINITIONS to be Deleted MEMBER(S) OF THE PUBLIC 1.24 MEMBER(S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the utility, it contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

SITE BOUNDARY 1.41 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.

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LR-N21-0065 LAR S21-04 LAR H21-06 UNRESTRICTED AREA 1.50 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY, access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or industrial, commercial, institutional, and/or recreational purposes.

2.5 Hope Creek TS Figures to be Deleted Figure 5.1.1 Exclusion Area and Unrestricted Areas and Site Boundary for Radioactive Gaseous and Liquid Effluents - See TS Page 5-2 of Attachment 3 Figure 5.1.2 Low Population Zone - See TS Page 5-3 of Attachment 3 2.6 Hope Creek TS Impacted by Deletion of DEFINITIONS and Figures TS 5.1.1 - EXCLUSION AREA AND MAP DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS - Deleted and replaced with new Section 5.1 - SITE DESCRIPTION TS 5.1.2 - LOW POPULATION ZONE - Deleted and replaced with new Section 5.1 - SITE DESCRIPTION New TS Section 5.1 added to replace TS 5.1.1 and 5.1.2:

5.1 SITE LOCATION Hope Creek Generating Station is located in Salem County, New Jersey along the eastern shore of the Delaware River approximately 8 miles southwest of Salem, New Jersey and 18 miles south of Wilmington, Delaware.

TS 6.8.4.g - Radioactive Effluent Controls Program - Replace capitalized font of the terms MEMBERS OF THE PUBLIC, UNRESTRICTED AREA and SITE BOUNDARY that are referenced within TS 6.8.4.g with normal (non-capitalized) font to reflect their deletion from TS DEFINITIONS.

2.7 Reason for the Proposed Change The requested amendment to delete the above-described DEFINITIONS in TS Section 1 and delete site figures contained in TS Section 5, Design Features, removes unnecessary information within the TS that is already contained in Licensee controlled documents. The proposed change to revise TS Section 5.1 to provide a text description of the location of the plant is necessary due to the deletion of the TS figures referenced in the current Section 5.1. These changes to both the Salem and Hope Creek TS are administrative in nature and are in alignment with NUREG-1431 and NUREG-1433 respectively relative to TS DEFINITIONS and descriptions of the site.

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LR-N21-0065 LAR S21-04 LAR H21-06 2.8 Descriptio n of the Proposed Change Attachments 1 and 2 depict the above-described changes for the Salem Unit 1 and Unit 2 TS respectively. Attachment 3 depicts the above-described changes to the Hope Creek TS. Attachment 4 provides proposed changes to the Salem Unit 1 and Unit 2 TS Bases that result from the proposed Salem TS changes described. Attachment 5 provides the proposed changes to the Hope Creek TS Bases that result from the proposed Hope Creek TS changes described. The TS Bases mark-ups in Attachments 4 and 5 are provided for information.

3.0 TECHNICAL EVALUATION

The proposed change deletes the TS DEFINITIONS for the terms MEMBERS OF THE PUBLIC, SITE BOUNDARY and UNRESTRICTED AREA. These terms are already defined within 10 CFR 20.1003 and are defined in the Offsite Dose Calculation Manual (ODCM) for both stations. Having these terms defined in the TS in addition to 10 CFR 20 and licensee-controlled station documents is duplicative. Deletion of the definitions from the TS does not affect the substance of any TS requirement, and the definitions are not needed for clarity as these terms are used in the TS. Deleting these terms as TS DEFINITIONS is administrative in nature, does not affect the design or operation of any plant Structures, Systems or Components (SSCs) and will also align the Salem and Hope Creek TS with NUREG-1431 and NUREG-1433 respectively relative to these specific terms in the TS DEFINITIONS.

The proposed change deletes diagrams in the Salem and Hope Creek TS that depict the site and surrounding area. These diagrams are legacy in their depiction and diagrams of this nature and supporting text are also contained in licensee-controlled documents such as the Updated Final Safety Analysis Reports (UFSAR) and ODCMs for both plants. In conjunction with the deletion of these diagrams is the proposed revision to TS Section 5.1 to provide a text description of the site location since the current TS descriptions reference the TS Figures being deleted. The associated diagrams and Section 5.1 references to the diagrams are not requirements of 10 CFR 50.36 (c)(4), Design Features of Technical Specifications. Replacement of these diagrams and references to them with a text description of the Site Location is administrative in nature, do not affect the design or operation of any plant SSCs and aligns the Salem and Hope Creek TS to NUREG-1431 and NUREG-1433 respectively relative to descriptions of the Site.

10 CFR 50.36 contains a set of objective criteria for determining which regulatory requirements and operating restrictions should be included in TS. The proposed deletions of TS DEFINITIONS and relocation of TS site figures will not impact any safety limits, limiting safety system settings, limiting conditions of operation or surveillance requirements as described in paragraphs (c)(1),(2), and (3) of 10 CFR 50.36. Therefore the deletion of these items from station TS conforms to the requirements of 10 CFR 50.36.

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4.0 REGULATORY EVALUATION

4.1 Applicable Regulatory Requirements/Criteria 10 CFR 50.36(c) contains a set of objective criteria for determining which regulatory requirements and operating restrictions should be included in TS. These criteria include Limiting Conditions for Operation (LCOs), Safety Limits (SLs), Limiting Safety System Settings (LSSSs) and Surveillance Requirements (SRs) associated with plant structures, systems and components (SSCs) that support the safety analyses of plant. The proposed change involves removing information from the TS that do not fit the requirements of 10 CFR 50.36 for inclusion in TS. The proposed text description of the Site Location is in alignment with the level of information necessary for this TS Section and is considered administrative in nature. All LCOs, SLs and LSSSs associated with plant SSCs remain unchanged from this proposed amendment.

All TS requirements for plant SSCs remain in accordance with 10 CFR 50.36(c). Therefore, the proposed changes are consistent with current regulations.

4.2 Precedents Removal of the site area maps and the definitions for MEMBER(S) OF THE PUBLIC, SITE BOUNDARY and UNRESTRICTED AREA(S) are established in the Improved Standard Technical Specifications detailed in NUREG-1431 and NUREG-1433 and reflected in the TS for multiple plants.

Amendments approving adoption of Improved Standard Technical Specifications have characterized the removal of defined terms as administrative changes. Additionally, amendments have been approved for deleting individual TS Definitions along with changes to Administrative Controls:

1. Letter from NRC to Joseph W. Shea, Sequoyah Nuclear Plant Units 1 and 2 - Issuance of Amendments for the Conversion to the Improved Technical Specifications with Beyond Scope Issues (TAC Nos. MF3128 and MF3129), dated September 30, 2015 (ADAMS Accession No. ML15238B460).

2. Letter from NRC to J. A. Scalice, Sequoyah Nuclear Plant, Units 1 and 2 - Issuance of Amendments Regarding Technical Specification Change No. 01-03 (TAC Nos. MB4660 and MB4661), dated February 11, 2003, (ADAMS Accession No. ML030430047).

The proposed changes to remove site area diagrams from TS are consistent with the following precedents:

1. Letter from NRC to M. Nazar, St. Lucie Plant, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 246 and 197 Regarding Technical Specifications Site Area Map (EPID L-2018-LLA-0198), dated November 2, 2018 (ADAMS Accession No. ML18274A224)

2. Letter from NRC to J. A. Stall, Turkey Point Units 3 and 4 - Issuance of Amendments Regarding Removal of Site Area and Plant Area maps from Technical Specifications (TAC Nos. MB1968 and MB1969), dated February 12, 2002 (ADAMS Accession No. ML020580442) 6 of 9

LR-N21-0065 LAR S21-04 LAR H21-06

3. Letter from NRC to J. A. Price, Millstone Power Station, Unit Nos. 1, 2, and 3 -

Issuance of Amendments RE: Administrative and Editorial Changes (TAC Nos. MB3394, MB3395, and MB3396), Dated September 17, 2002 (ADAMS Accession No. ML022000322)

4. Letter from NRC to C. R. Hutchinson, Arkansas Nuclear One, Unit No. 2 - Issuance of Amendment RE: Design Features and Administrative Controls (TAC No. MA2403),

Dated May 19, 1999 (ADAMS Accession No. ML021560327)

5. Letter from NRC to R.E. Denton, Issuance of Amendments for Calvert Cliffs Nuclear Power Plant, Unit No. 1 (TAC No. M88429) and Unit No. 2 (TAC No. M88430), Dated March 14, 1995, (ADAMS Accession No. ML010580033) 4.3 No Significant Hazards Consideration Analysis The proposed changes delete specific DEFINITIONS within the Salem Generating Station (Salem) and Hope Creek Generating Station (Hope Creek) Technical Specifications (TS). The DEFINITIONS for the terms MEMBER(S) OF THE PUBLIC, SITE BOUNDARY AND UNRESTRICTED AREA(S) are already contained in the Offsite Dose Calculation Manual (ODCM) for both the Salem and Hope Creek sites as well as in 10 CFR 20.1003. The proposed change also removes associated TS Figures that depict the Salem and Hope Creek sites and surrounding areas since diagrams of this nature and supporting descriptive text can be found in the Updated Final Safety Analysis Reports for both stations. The changes do not affect any system, structure or component nor does it alter any requirement relative to plant operations, hence the changes do not involve any significant hazard.

The discussion below addresses each criterion and demonstrates that the proposed amendment does not constitute a significant hazard.

1. Do the proposed amendments involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No.

The requested changes deletes the DEFINITIONS for MEMBER(S) OF THE PUBLIC, SITE BOUNDARY, and UNRESTRICTED AREA(S) from the Salem Generating Station and Hope Creek Generating Station TS. The requested change also removes diagrams of the Site and surrounding area from the Salem and Hope Creek TS.

These requests involve changes that are administrative in nature. No actual plant equipment, accident analyses or dose consequences will be affected by the proposed changes.

Therefore, the proposed amendments do not involve a significant increase in the probability or consequences of an accident previously evaluated.

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2. Do the proposed amendments create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No.

This request involves administrative changes to the Salem and Hope Creek TS to remove the DEFINITIONS for MEMBERS OF THE PUBLIC, SITE BOUNDARY and UNRESTRICTED AREA(S) as well as remove TS Figures of each site and surrounding area.

The changes are administrative in nature and no actual plant equipment or accident analyses will be affected by the proposed changes and no new failure modes or accident initiators will be created.

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

3. Do the proposed amendments involve a significant reduction in a margin of safety?

Response: No.

This request involves changes to the Salem and Hope Creek TS to remove DEFINITIONS and diagrams of each site and surrounding area. The proposed changes are consistent with NRCs regulations set forth in 10 CFR 50.36 as well as the Standard Technical Specifications found in NUREG-1431 and NUREG-1433.

The changes being proposed are administrative in nature. Margins of safety are associated with confidence in the ability of the fission product barriers to limit the level of potential dose to the public. No actual plant equipment or accident analyses will be affected by the proposed change. Additionally, the proposed changes will not relax any criteria used to establish safety limits, will not relax any safety systems settings, nor will they relax the bases for any limiting conditions of operation.

Therefore, the proposed amendments do not involve a significant reduction in the margin of safety.

Based on the above, PSEG concludes that the proposed amendments present 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.

4.4 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.

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5.0 ENVIRONMENTAL CONSIDERATION

A review has determined that the proposed administrative amendment does not change any requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, nor does it change an inspection or surveillance requirement. The proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b),

no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.

6.0 REFERENCES

1. NUREG-1431, Standard Technical Specifications - Westinghouse Plants, Revision 5.

2. NUREG-1433, Standard Technical Specifications - General Electric Plants (BWR/4), Revision 4.

3. 10 CFR 50.36 - Technical Specifications

4. 10 CFR 20 - Standards for Protection Against Radiation 9 of 9 LAR S21-04 LR-N21-065 LAR H21-06 Mark-up of the Current Salem Generating Station Unit 1 Technical Specification Pages The following Technical Specifications pages for Renewed Facility Operating License DPR-70 are affected by this change request:

Technical Specification Page INDEX I INDEX XVII DEFINITIONS 1-4 DEFINITIONS 1-6 DEFINITIONS 1-7 5.0 5-1 Figure 5.1-1 5-2 Figure 5.1-2 5-3 Figure 5.1-3 5-3a 6.8.4 6-19a 6.8.4 6-19b 1

INDEX DEFINITIONS SECTION PAGE 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 CORE ALTERATION .............................................................................................................1-2 CORE OPERATING LIMITS REPORT .................................................................................1-2 DOSE EQUIVALENT I-131 . .. .. ...........................................................................................1-2 DOSE EQUIVALENT XE-133. .. ...........................................................................................1-3 ENGINEERED SAFETY FEATURE RESPONSE TIME .......................................................1-3 FREQUENCY NOTATION .. .. .. ...........................................................................................1-3 FULLY WITHDRAWN .......... .. .. ...........................................................................................1-3 GASEOUS RADWASTE TREATMENT SYSTEM ................................................................1-3 IDENTIFIED LEAKAGE ....... .. .. ...........................................................................................1-3 INSERVICE TESTING PROGRAM .......................................................................................1-4 MEMBER(S) OF THE PUBLIC .. ...........................................................................................1-4 OFFSITE DOSE CALCULATION MANUAL (ODCM) ...........................................................1-4 OPERABLE - OPERABILITY . .. ...........................................................................................1-4 OPERATIONAL MODE - 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 1 Amendment No. 337

DESIGN FEATURES

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

SECTION 5.1 SITE SITE LOCATION.................................................5-1 Exclusion Area * . * . * * . . . . . * * . * . * . * * . . * . * * * . * * . * * . . . . . . * * . . . . . . . . 5-1 Low Population Zone . . . . . . * . . . . . . . * * . . * . * * . . . . . . . . * . . . . * . * . . . . . . 5-1 Unrestricted Areas for Radioactive Gaseous and ..

Liquid Effluents * . * . * * * . * . * * * * * * * * * * * * . * * * . . . . * * . . * * . . . . * . . . . . . 5-1 5 2

. CONTAINMENT Configuration * * * . * * * * * * * .. * * * * * * . . * * . * * * * . . . . . * . . . . . . . * . . . * . . . . . 5-1 Desi_gn Pressure and Temperature * * . . . * . * * * . . . . . . * . . . . * * * . . . * * . .

5-4 5.3 REACTOR CORE Fuel Assemblies . * . . * * . * * . . * * * . * * . * * * * . * . . * . * . * * * . . * . . * . * * . * . . .

5-4 Control Rod Assemblies * . * . * * * . . . * * * * . * * . * . . . . . * * . . * . . . * * * . . . . .

5-4

5. 4 REACTOR COOLANT SYSTEM Design Pressure and Temperature . * . * * * * * * * * * . . . . * * . . . . . . * * . * . . * . 5-4 5.5 METEOROLOGICAL TOWER LOCATION .................................. 5-5 5.6 FUEL STORAGE Criticality * . * * * * . * * . * * . . * * . . . * * . * * . * . . * . * * * . * * * . . . * . . . . . . . . * . . 5-5 Drainage * * * * * . . . * . . * * . * * . . * * * . . * . . . * . * . * * * . * * * * * . . . * * * * * . . * * * . . 5-6a Capacity * . * . * . . . . * * * . . * . . * * * * * . . * * * * . * * . . . . * * . * * * * . . . . * * * . * * * .

5-6a 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT . . . . . . * . * . * . * . . . * . . . * . . * . . . . 5-6a SALEM - UNIT 1 XVII Amendment No. '2@

DEFINI':':ONS

b. LeakcH:JR ir:i--_o the- containrrcnt at:ncsphere f.::o:n scurce::; :_!:at_ a:c> botJ1 s_peclfica:__ly located '3-:ld known eithe:::: not to :'._r_terfere w_Lh __

t he o_perat io r : of leakage detection systems or not :-_o be p;-<_i,;S:iUkE BOTJt-.;rJT1RY .AKAGE, o::::

c. React er coolant systen lec;.kuge :hrou<J"l a steat1 g ener a :-_ ( r to t-*H; secondary system (pr:'..nilry-to-secor_dary leakage).

INSERV121:. ':'ESTTC:; PROGI\AM

5. 1 T'.-le INSERV:CE TESTING ?RO-'.?AM is tl:e licenHee program :-l:at fulfills the ::::equire'.Tlents c: _:_u Ct'R c,n

. 55a (f).

tv'.EMBER(S} OF 'l'Hl'.'. PUBLIC 1.16 MEMBSR (S) o-;c THE PUBLIC sr.a_:_1 be all those persons wi--:o are not Not Used occ._1pc.t::..or!n_:_1y asscciateci '"'it:-i :-r.e plant. This category does ::::1ot include e:nployees of PSE&S, its contac -o-rs, or ver.dors . .i\lso excluo.ed from t."Jis ca:egory are pe::-H Jns who ent 0r -_r_e site tc service equipner.t or to make de2-:'..veries. Thls cat ego:y does :nclnde p(c-rsons ""fr10 *:ise porticr.s of t:'1e s:'..te f::;r re*:reationa1, cccupational, or ot:1cr pc:rposes not GJ.ssociated ....,ith tr_e plnr:t.

OFF'STTE DOSE CALcu_:_,A' l ' l ON MA:\--.:AL (OLlCM}

1. 17 The OFFSITE DOSE CALCULA':'ION MP..NUAL (O:JCM) sh2.ll ccr_ _ai:-1 the metc1cdclogy and pararr.ete::-s *:ised in the calculatio:1 of o:fsite doses re su1tir_g fvo:n radioa::: tive gaseo1..s anci liquid e:fluent:;, :'.r: th e calcula:-on of gaseo-Js and liqc:ld effluent monito::-ing r, larrr. / T :::-ip setpoints, and in the conduct of :f. 'e Env:'..ronme:1tal ?adlologico.l Mc:>r:_Loring ?rcg ram. The> ODC shall also con::-_a:'_n (1) the Radioac:'.ve Effl*Jent ccntrols ar.d P.ao.iological i':nvi::-onnental Mor. i tor ing prograrr.s .:::-e quired by Secticn 6. 8. 4 a::-id (2) descri!Jt:'..ons of the i nfornation that should be i::-ic_:_uded in :r.e Ann*:ial Radic_ogica_ Envi::-o::-imer.'::al Operating ano. A:--1::::,ual Raciioacl_ve Effl. * .1er.::_ Release Reports req1_'._red Dy Spec:'.__:'._'_callo.: 1s 6.9.l.7 a:1d 6.1.::..B ::-c>c-;pe:tiv01y.

OPERABLE - OPF'.RABILITY I .18 A systen, subsystem, :rain, component, or o.evice shall be OPERABL or

,1ave 0!:'£1\ABI_:_,:TY '.-.1he:1 il is capable oi" performing ils specified safety

_:1_:nct10::-i(s) a ncl *.-.*'1er, a; r_ecessa-y a-_*_endant i*1str-,inen-:ation1 c:ont.rols, r:orrr.al or 0m0-gency electrica_ power, coolir:g and seal water, _ubrica:'_on, a:1d o:he auxiliecry e qui me:1 t ::ha:: iire re quired '.:or the Hyste'.11, s*.1bsystem, ::rain, componer,:, or d.evice to perfo.::m 1ls speclfleci. see.fely fL,r.ct_lon(s) ae also capable J: performing tl-'.c-ir related sc:pport fu:-iction(s).

OPERA lOt>.J.LiL MOC!'.: - MOD.O:

1.19 Ar. OPERA':'IONAL M0=1E {i.e., MODE) shall cor r e spond tu any one inclus_ve co'.Tlbina;::ion of core reacllvlly cond_t_lon, oov-1er leve:__ and average .::eaclcr coclanc te:npera_i;re specif.led in ':'able 1.1.

SA',F'.'1 - UNIT ;__ 1-4 .limeno.:ner. No. 319

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 Not Used 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 Not Used SOURCE CHECK 1.31 SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to either {a) an external source of increased radioactivity, or(b) an internal source o f radioactivity (keep-alive source), or (c) an equivalent electronic source check.

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. 280

D!PINITIONS

b. Tiie teating of one

Y*tem . *ub*ystem, train, or other de*ignAted COlllPOllent at th* beginning of each subinterval.

MRMAL i>OW'ER 1.33 :"HER.MA.:. POWER shall be the total reactor core heat tra.n*fer rat to the reactor coolant.

\/NPENTIFI£p LEMAG:S l.34 UNIDEN"i'IFIED LE.AX.AGE shall be all leakage '.except Reactor Coolant Pump Seal Water InJect1on) which l9 not IDENTIFIED LEAKAGE.

tJNl'.ESIJl.IC'ED )),llEh 1.35 An UNRESTRICTED AREA shall be any area at or beyond the S ITE BOUNDARY. Not Used access to which is not controlled by the licensee for purpoaes of protection of individuals from exposure to radiation and radioactive m&teriala, or a.ny area within the SITE BOUNDARY used for residential quarters or indu*trial, commercial, inst1tut1onal, and/or recreation.al purposes.

\fENII!.AIION WWJST '!'UATMENI SYSUM 1.36 A VENTILATION EXHAUST TREATMENT SYSTEM shall be any *Y*tem designed and installed to reduce gseoua radioiodin* and radioactive material in particulate form in effluents by pa**ing ventilation or vent exh.au*t ga*ea through charcoal adaorhers and/or KBPA filters for the purpose of removing iodines or particulates from the 9aseou

exhaust stream prior to the release to the environment (such a system i* not con*idered to have any effect on noble gas effluents) . Engineered Safety Featur 'CF) atmo*pheric cleanup systema are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

\fENIING 1.37 VENTING shall be the controlled proc*** of discharging air or gaa from a confinement to maintain temperature, preaaure, humi dity, concentration, or other operating condition, in such a manne r that replacement air or gas is not provided or required during VENTING. Vent, used i system names, does not imply a VENTDIO proceaa.

SALEM - UNIT l 1-7 Amendment No. 1 73

5.0 .DESIGN FEATURES 5.1 SITE LOCATION 5.1 SITE Salem Generating Station is located in Salem County, New Jersey along the eastern shore of the Delaware River approximately 8 miles southwest EXCLUSION AREA of Salem, New Jersey and 18 miles south of Wilmington, Delaware.

5,1.1 The exclusion area sh.all be shown in Figure 5.l.l LOW POPULATION ZONE

. 5.1.Z The low population zone shall be as shown in Figure 5.1-2.

Q UNRESTRICTED AREAS FOR RADIOACTIVE GASEOUS AND LI UID EFFLUENT'S 5.1.3 UNRESTRICTED AREAS within the SITE BOUNDARY that are accessible to

MEMBERS OF THE PUBLIC, shall be as shown in Figure 5.1-3.

5.2 CONTAINMENT CONFIGURATION 5.2.1 The reactor containment building is a steel 11ned, reinforced cortcrete building of cylindrical shape, with a dome roof and having the following design features:

a *. Nominal inside diameter

140 feet.

b. Nominal inside height a 210 feet.

c. Minimum thickness of concrete walls

4.5 feet.

d. Minimum thickness of concrete roof

3.5 feet.

e. Minimum t*ickness of concrete fl oo t mat

16 feet.

f. Nominal thickness of steel liner

1/4 to 1/2 inch.

g. Net free volume

2.62 x 106 cubic feet.

SALEM

UNIT 1 5-1 Amendment No. 59

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Amendment lo. 59 SALE°" - N[T 1 5-3a

ADMINISTRAT!VE CONTROLS following testing in accordance with is program, the leakage a:e acceptance criteria are less than or equal to 0.6 Type C tests and less than or equal to a.75 L, L. for ':;/pe 3 ac for Type A t:est:s;

b. Air lock testing acceptance criteria are:

1) overall air lock leakage rate is less than or equal to a.as -.

when tested at greater t:han or equal to P,,

2) Seal leakage rate less than or equal to a.al L, per hour when the gap between the door seals is pressurized t:o la.a psig.

Test frequencies and applicable extensions will be controlled by t:he Primary Containment Leakage Rate Testing Program.

The provisions of Specification 4.a.3 will be applied to the Primary Containment Leakage Rate Testing Program.

6.8.4.g Radioactive Effluent Controls Program A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to the MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements: members of the public

1) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM,

2) Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR 20, Appendix B, Table II, Column 2, unrestricted areas

3) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.105 and with the methodology and parameters in the ODCM, member of the public

4) Lim.i.tations on the annual and quarterly doses or do.se commitment to a MEMBER.. OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50,

5) Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days.

6) Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when.the projected doses in a 92-day period would exceed a suitable fraction of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50, SALEM - UNIT 1 6-19a Amendment No. 234

ADMINISTRATIVE CONTROLS

7) Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B, Table II, Column 1, site boundary

8) Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, member of the public

9) Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, site boundary

10) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

6.8.4.h Radiological Environmental Monitoring Program A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM, site boundary

2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of the census, and

3) Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

6.8.4.i Steam Generator (SG) Program An SG Program shall be established and implemented to ensure that SG tube integrity is maintained. In addition, the SG Program shall include the following:

a. Provisions for condition monitoring assessments. Condition monitoring assessment means an evaluation of the as found condition of the tubing with respect to the performance criteria for structural integrity and accident induced leakage. The as found condition refers to the condition of the tubing during an SG inspection outage, as determined from the inservice inspection results or by other means, prior to the plugging of tubes. Condition monitoring assessments shall be conducted during each SALEM - UNIT 1 6-19b Amendment No. 338 LAR S21-04 LR-N21-0065 LAR H21-06 Mark-up of the Current Salem Generating Station Unit-2 Technical Specification Pages The following Technical Specifications pages for Renewed Facility Operating License DPR-75 are affected by this change request:

Technical Specification Page INDEX I INDEX XVII DEFINITIONS 1-4 DEFINITIONS 1-6 DEFINITIONS 1-7 5.0 5-1 Figure 5.1-1 5-2 Figure 5.1-2 5-3 Figure 5.1-3 5-3a 6.8.4 6-19a 6.8.4 6-19b 1

INDEX DEFINITIONS SECTION PAGE 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 CORE ALTERATION ... .. .. .. ................................................................................. 1-2 CORE OPERATING LIMITS REPORT ................................................................... 1-2 DOSE EQUIVALENT I-131 .. ................................................................................. 1-2 DOSE EQUIVALENT XE-133 ................................................................................. 1-3 ENGINEERED SAFETY FEATURE RESPONSE TIME ......................................... 1-3 FREQUENCY NOTATION . .. ................................................................................. 1-3 FULLY WITHDRAWN .. .. .. .. ................................................................................. 1-3 GASEOUS RADWASTE TREATMENT SYSTEM .................................................. 1-3 IDENTIFIED LEAKAGE .. .. .. ................................................................................. 1-3 INSERVICE TESTING PROGRAM......................................................................... 1-4 MEMBER(S) OF THE PUBLIC ............................................................................... 1-4 OFFSITE DOSE CALCULATION MANUAL (ODCM) ............................................. 1-4 OPERABLE - OPERABILITY ................................................................................. 1-4 OPERATIONAL MODE - 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. 318

DESIGN FEATURES

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

SECTION 5.l SITE Site Location..............................................................................5-1 Exclus'ion Area . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 Low Population zone * . * . * * * * * * . . * . * * . . . . . . . . . . . * * * . . . . * . . . . . . . .

5-1 Unrestricted Areas for Radioactive Gaseous and Liquid Effluents * . . * . . . . . * . * * . . . * * * . . . . * . . . . . . . * . . * . . . * . . . . * . . * . . . . * . . 5-1 5

2 CONTAINMENT Configuration * . * * . . * * * * . * * * * * * . . . . * * . * . * . . * * . . * . . * . * . * . * . . . . . . . 5-l Design Pressure and Temperature . . . . * . . . . . * . . . * . . . . * . * . . * . . * . * . . 5-4 5.3 REACTOR CORE Fuel Assemblies 5-4 Control Rod Assemblies . . . . . . . . . . . * . . . . . . . . . . . * . . . . . . . . . * . * . . * . . 5-4 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature . * . . . * * . * . . . . . * * . . . . . . * . . . . * . . . . 5-4 5.5 METEOROLOGICAL TOWER LOCATION * * * * * * * , , . * , * * * . * * * * * * * * * * * * . * * * *

5-5 5.6 FUEL STORAGE

Criticality . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..

. . . . 5-5 Drainage . . . . . . * * * . * * . * . . . . . * . . . . . . . * . . . * . . . . * * * * . . . . . . * . . . . . * .

5-5b Capacity . . . . * * . * . . * * * . . . . * * . * . . . . . * * . . . . . * . . * * * * . * * . . * * . * . . . . . . 5-5b 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT . . . . * . . . . . * * * * . . * . * . . . . . . . . . 5-5b SALEM - UNIT 2 XVII Amendment No. 250

DEFINI'°='=ONS

b. L e a kaqe into the co:ltu:'._r.rrent attosphere frori sources r.hnt dr-f' bet!:

sp<-'c' :'cal ly located ar.d know:-1 either :1ct :'._ntefere 'e.'ith tr_e opera_ t_ _'._ or: of ::.enknge df-'tection sy st c :n :; or no-: t1 De P ? ESS::RE BO:::\CARY LE!\K!1C;E, o:

c. Reactor oolnnt syste:-n le a k a gp ;_!: rough a steam qenerator to the seco::-i::lar y sys Lerr (p.:: L:nar 1- Lo-secu 1dnr y len kage)

1. 15. 1 The I t-.; S ER \-' CE l'ES'l'l:\( i:'i-\OCPAM is :_f:e 11ce:1see prugram tLat f1Jlfi_i_ls the requiremer: -s of 1() C: FR 0,<;. _')5n ( f)

'1"'BER(S) OF THE PUBLlC 1.16 MEMBER(S) CF THE PUBLIC shall be ull those per s ons wl;o a.:: e not__ Not Used occlJpat:'._::;r.a::.1*1 ussociated with the plant. Tr.is category does :iot inclucie emplcyees o: PSt:&G, i:__ s conlraclcrs, or veridors. Als o f-'X:lud.ed from this catf-'gcry ar0 pt'rsor.s who enter t'le site to se-rvice equip1:1ent or -:o rr.ake de_:'._veri'O's. r his calegory does iriclude persons 'dhO -.1Sf-' portio1s of the site fo:::

recreational, occc:pat:'..or.al, o::- ctc1er pu::-poses not associat_eci wiLh Lhe pla:1:..

FFSTTE JOSE CALCULAT:ON MANUAL (ODC) 1.17 The OFFSITE DOSE C.>\LC!JLATION M ANUAL ( ODCM) sfia ll cor,tain the l'leth odcJlcgy and parameters used ir: t-_he calc-1lci,.._ion of Jffsite doses res1Jlti'.lg from rad :oa cti ve gasec1s and liqlJid ef:lc:cnt:o, i:l the ca lc-J l a-: _'_ on of gaseous and ::_::_quid effluent moni>::-.cring !ila rm/Tri p S c tpoi nts, and in the condlJct of the Environmental Pad_io:_ogical Mc-ni:: crin g Prog::-a:n. The DCC\.1 ::;hall also contain (1) th e R?dioactive Efflc:ent conlrols ci!ld Ra di ol ogi ca_:_ Enviror.riental Monitcri119 1rograms r equi red by S ect:'.. on 6.8.4 acid (2) descri:utiocs of t'1 e :'_r_fo:::matiJ-'i :_!:at shYJld be incl*Jded in the Annc;al Rac.iological J:.nvio:11:1er.tal Opera::ing anci AnnL.al Padioactive l'.:ff_'._1;ent Release 2.epo.::ts required by Spec_'_:icatio:-is 6.9.l. / a:-id 6.9.l.8 respectively.

DPER!iBI,E - OPF.RABlLl'l'f 1.18 A syst,e:-n, s ub s y st e:n , trair:, componro1-: or device sf'.all be OPER.i\RLE or !:ave OPERA-! l'rY wec it ls capable of nerfor:-n_'._r_ ils s p eci:_'._ e d safety funclion(s), and wf1er_ nll llf-'Cf-'ssary attenda:-i-:: instrlJmentat'or., controls, normal or eme rge:1cy e:_cc::trical powe-r so*Jrce, cco_ing ano. seal wate::, l*Jbrication er othe:: auxi ;ayy equipme:-il Lhar_ a re rf-'q11ir ed :or thP system, sul1system, t-_rain, componPnt )r device to per-term its specit:'..ed safety tunction(s} are ulso capable ct per f'>r :nin g ::hei::- rR l ;o t c d si:pport_ fnncticr. (.s).

OPERATONAL MOCE - MO DE 1.19 An OPERfl.'C'ICNAL '10D1' (i. c . ' O D F. } sha. co-r-respond to any on e in cllJs i v combinntion of core reactivity condi-:_'_on, po'"er level and average reactor coolant tempera-:c:re specified i::-i Tabe .l.

SAL:i:M - UNIT 2 1-4 Amendf'.Lenl :o.Jo.300

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 Not Used 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 Not Used SOURCE CHECK 1.31 SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to either (a) an external source of increased radioactivity, or(b) an internal source of radioactivity (keep alive source), or (c) an equivalent electronic source check .

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. 263

DEFINITIONS

b. Thll te*ting of one system, subsystem, train, or other designated component at the beg1nn1ng of each subinterval.

'llERMN. POWiR 1.33 THERMAL POWER shall be the total reactor core heat tran sfer rate to the reactor cool ant .

UNIDENTIFIED LEAKAGE UNIDENTIFIED LEAKAGE sha ll be all le ak age I

1.34 (except Reactor Coolant Pump Seal Water !nJection) which is not IDENTIFIED LEAKAGE.

UNBESIRICTED AREA 1.35 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY, Not Used access to which is not controlled by the license for purpo*e* of protection of individuals from exposure to radiation and radioactive materials, or any area w ith in the SITE BOUNDARY used for residential quarters or industrial, commercial, institutional, and/or recreational purposes.

YENTILATION EXHAQST TREAIME!!T SYSTEM 1.36 A VENTILATION EXHAUST TREA'Il'IENT SYSTEM *hall b e any oystem designed and installed to reduce gaseous radioiodine and radioactive material in pa rtic ula te form in effluents by passing ventilation or vent exhaust gases through charcoal a dsorb ero and/or HEPA filters for the purpose of removing iodines or parti cula te* from the gaseou* exhau*t stream prior to the release to the environment (such a syatem is not con*idered to have any effect on noble gas effluents) . Engineered Safety Feature IESFI atmo*pheric cl eanup systems are not considered to be VENTILATION EXHAUST TREA'Il'IENT SYSTEM components.

VENIING 1.37 VENTING *hal l be the controlled process of discha rgin g air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or ot her operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system n am es, does n ot imply a VENTING proce***

SALEM - UNIT 2 1-7 Amendment No. 159

s.o DESIGN FEATURES 5.1 SITE LOCATION Salem Generating Station is located in Salem County, New Jersey along the 5-.l SITE eastern shore of the Delaware River approximately 8 miles southwest of EXCLUSION AREA Salem, New Jersey and 18 miles south of Wilmington, Delaware.

s.1.1 The exc:luslan area shall be shown In. Figure 5.1.l LOW POPULATION ZONE s.1.z Th* law population zone shall be as shawn In Figure 5.1-2.

UNRESTRICTED AREAS FOR RADIOACTIVE GASEOUS AND LfgUID EFFLUENTS I

5.1.3 UNRESTRICTED AREAS within the SITE BOUNDARY that are ac:c:esslble to MEMBERS OF TM£ PUBLIC, shall be 11 shown in Figure 5.1-3, 5.2 CONTAINMENT CONFIGURATION s.2.1 The reactor c:ontalnment building Is a steel lined, reln forc:td concrete

building of c:yllndrical shape, .with a dome roof and* having th* follaw1ng design featur11:

a. Ncmrtnal 1ns1de diameter * .140 f11t.

b. Nonrtnal Inside height

210 feet.

c:. Minimum thickness of c:onc:r*t* walls

4,5 fe*1e.

d. Minimum th1c:kness of c:onc:rete roof

3.5 f11t.

- M1nlmu111 thlc:kness.af c:onc:rete flaar mat

15 fe1t.

f, Nominal thlc:kn11s af st"l lln1r

1/4 to 1/2 lnc:h.

g, Net free volume

2.52 x 105 cubic: f1et.

SALEM

UNIT 2 5-l Amendment No. 28

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Intentionally Left Blank

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UHt"l' 2 Amendment No. ZS

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IJNtT Z AnMlndment Na. ZS

--1.DMINISTRATIV! CONTl!Ot.S acceptance criteria are less :han or equal to 0.6 t., for Type s and '!YP* c tests and less than or equal :o 0.75 L, for Type A

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b. Air lock testing acceptance criteria are:

l i overall air lock lealcag* rate is lH* than or equal to . :s .

when tHt*d at greater than or equal to P,,

2) Seal lee)cage rete l*** than or *CNal to O.Ol L, per hour when the gap between the door seals is'pressurized to 10.0 P**g.

Test frequencies and applicable extensions will be controlled by t*

Primary Conta1nment Leakage Rat* Testing Progr11111.

The provisions of Specification 4.0.3 will be applied to the Prl!Nlry Containment Leakage Rate Testing Program.

members of the public 6.8.4.g Radioactive Effluent controls Progr&111 A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses co the MElllE!U OF Tl!E PUBLIC from radioactive effluancs as low as reasonal:lly achievable. The program <ll shall be contained in the ODCM, (2) shall be ilr;llemented by operating procedure&, and (31 shall include remedial actions to be taken whenever the program limit* are exceeded. The program shall include th*

fol:owing el1111e 1 ncs:

l) Limitations on th* operal:>ilicy of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and aecpoint determination in accordance with the methodology in the ODCM.

21 Lim.i.tationa on th* concentrations of radioactive material released in iquid effluent* co lJNl\ESTRICTJa) AREAS conforming to 10 CFR 20, Appendix a, Table II. Colwr.n 2. unrestricted areas 31 Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM.

41 Limitations on the annual and quarterly doses or dose coll'lllia11ent to a MJCMBER.OF TllE PUBLIC from radioactive materials in liquid effluents released from each unit to llmlSS'l'l'.ICTEtl AREAS conforming to Appendix I to 10 CFR Par: sc. member of the public Sl Determination of CWlllllative and projected dose contributions from radioact1ve effluents for th* current calendar quarter and currant calendar year 1n accorl!ance with the methodology and parameters in the ODCM at least every 31 days.

61 Limitations on the operal:li1ity and use of the liquid and ;aseoua effluent treatment sy*t- to ensure that th* appropriate portions of th*H systems aro used co reduce rel***** of radioactivity when th* projected do*** in a 92-day period would exceed a suitable fraction of th* guidelines tor ehe annual dose or dose conmitment confoZ'll\in; to Appendix I eo lO C?R Part 50, SALEM

UNIT 2 6-l9a Amendment No. 215