LR-N21-0065, 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

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:	David Mannai 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)

Text

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, 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

Mannai, David Digitally signed by Mannai, David Date: 2021.09.29 10:49:16 -04'00'

LR-N21-0065 LAR S21-04 LAR H21-06 1 of 9 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

LR-N21-0065 LAR S21-04 LAR H21-06 2 of 9 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.

LR-N21-0065 LAR S21-04 LAR H21-06 3 of 9 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.

LR-N21-0065 LAR S21-04 LAR H21-06 4 of 9 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.

LR-N21-0065 LAR S21-04 LAR H21-06 5 of 9 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.

LR-N21-0065 LAR S21-04 LAR H21-06 6 of 9

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)

LR-N21-0065 LAR S21-04 LAR H21-06 7 of 9

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.

LR-N21-0065 LAR S21-04 LAR H21-06 8 of 9

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.

LR-N21-0065 LAR S21-04 LAR H21-06 9 of 9

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 LAR S21-04 LR-N21-065 LAR H21-06 1

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

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 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@

SITE LOCATION.................................................5-1

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 ior: 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 gener 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 c, n

. 55a (f).

the ::::equire'.Tlents c:

_:_u Ct'R tv'.EMBER(S}

OF

'l'Hl'.'. PUBLIC is tl:e licenHee program

-l:at fulfills 1.16 MEMBSR (S) o-;c THE PUBLIC sr.a_:_1 be all those persons wi--:o are not 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 ent0r

-_r_e site tc service equipner.t or to make de2-:'..veries.

Thls catego: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'lON 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 resu1tir_g fvo:n radioa:::tive gaseo1..s anci liquid e:fluent:;,

'.r:

the 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 ?rcgram.

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.:::-equired 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) ancl *.-.*'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 equime:1t

ha::

iire required

'.: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 correspond 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 Not Used

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

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

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

SITE BOUNDARY 1.29 The SITE BOUNDARY shall be that line beyond which the land is not

owned, leased, or otherwise controlled by the licensee, as shown in Figure 5.1-3, and which defines the exclusion area as shown in Figure 5.1-1.

SOLIDIFICATION 1.30 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 1 1-6 Amendment No.

280 Not Used

D!PINITIONS

b.

Tiie teating of one *Y*tem.

• ub*ystem,

train, or other de*ignAted COlllPOlent 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 SITE BOUNDARY.

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 Featuro

'pCF) 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, humidity, concentration, or other operating condition, in such a manner 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 Not Used

5.0.DESIGN FEATURES 5.1 SITE EXCLUSION AREA 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.

UNRESTRICTED AREAS FOR RADIOACTIVE GASEOUS AND LIQUID 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 oot 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 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.

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SALE°" -

N[T 1 5-3a ANIA I

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Intentionally Left Blank

ADMINISTRAT!VE CONTROLS

b.

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

1) lock testing acceptance criteria are:

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:

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,

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,

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 members of the public unrestricted areas member of the public

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,

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,

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,

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,

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 site boundary member of the public site boundary site boundary LAR S21-04 LR-N21-0065 LAR H21-06 1

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

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 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 Site Location..............................................................................5-1

DEFINI'°='=ONS

b.

Leakaqe 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

'._nteefere 'e.'ith tr_e opera_ t_ _'._or: of

.enknge df-'tection systc:n :;

or no-:

t1 De P?ESS::RE BO:::\\CARY LE!\\K!1C;E, o:

c.

Reactor `oolnnt syste:-n leakagp ;_!: 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 It-.;SER\\-' 6CE l'ES'l'l:\\(G i:'i-\\OCPAM is

_f:e 11ce:1see prugram tLat f1Jlfi_i_ls the requiremer: -s of 1() C:FR 0,<;. _')5n ( f)

'1"'HBER(S)

OF THE PUBLlC 1.16 MEMBER(S)

CF THE PUBLIC shall be ull those persons wl;o a.::e not __

occlJpat:'._::;r.a::.1*1 ussociated with the plant.

Tr.is category does

iot inclucie emplcyees o:

PSt:&G, i:__s conlraclcrs, or veridors.

Also 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.

rhis calegory does iriclude persons 'dhO -.1Sf-' portio71s 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) sfiall cor,tain the l'leth odcJlcgy and parameters used ir:

t-_he calc-1lci,.._ion of Jffsite doses res1Jlti'.lg from rad:oactive gasec1s and liqlJid ef:lc:cnt:o, i:l the calc-Jl a-: _'_ on of gaseous and ::_::_quid effluent moni>::-.cring !ilarm/Trip Sctpoints, and in the condlJct of the Environmental Pad_io:_ogical Mc-ni::cring Prog::-a:n.

The DCC\\.1

hall also contain (1) the R?dioactive Efflc

ent conlrols ci!ld Radiologica_:_ Enviror.riental Monitcri119 1rograms r equired by Sect:'..on 6.8.4 acid (2) descri:utiocs of t8'1e :'_r_fo:::matiJ-'i

_!:at shYJld be incl*Jded in the Annc;al Rac.iological J:.nvieo: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, subsyst 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 speci:_'._ed safety funclion(s),

and wf1er_ nll llf-'Cf-'ssary attenda:-i-::

instrlJmentat'or.,

controls, normal or emerge:1cy e:_cc::trical powe-r so*Jrce, cco_ing ano. seal wate::,

l*Jbrication er othe:: auxi

ayy equipme

-il Lhar_ are rf-'q11ired :or thP system, sul1system, t-_rain, componPnt )r device to per-term its specit:'..ed safety tunction(s}

are ulso capable ct perf'>r:ning ::hei::-

rRl;otcd si:pport_

fnncticr. (.s).

OPERAT*ONAL MOCE -

MODE 1.19 An OPERfl.'C'ICNAL '10D1' ( i. c. ' HODF.}

sha.

co-r-respond to any one incllJsi v9 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 Not Used

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

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

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

SITE BOUNDARY 1.29 The SITE BOUNDARY shall be that line beyond which the land is not

owned, leased, or otherwise controlled by the licensee, as shown in Figure 5.1-3, and which defines the exclusion area as shown in Figure 5.1-1.

SOLIDIFICATION 1.30 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 Not Used

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 coolant.

UNIDENTIFIED LEAKAGE 1.34 UNIDENTIFIED LEAKAGE sha ll be all le akage (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, access to which is not controlled by the licens2e for purpo*e* 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.

YENTILATION EXHAQST TREAIME!!T SYSTEM 1.36 A VENTILATION EXHAUST TREA'Il'IENT SYSTEM *hall be any oystem designed and installed to reduce gaseous radioiodine and radioactive material in particula te form in effluents by passing ventilation or vent exhaust gases through charcoal a dsorbero 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 cleanup systems are not considered to be VENTILATION EXHAUST TREA'Il'IENT SYSTEM components.

VENIING 1.37 VENTING *hal l be the controlled process of discharging air or gas from a confinement to maintain temperature, ot her operating condition, in such a provided or required during VENTING.

imply a VENTING proce***

SALEM -

UNIT 2

pressure, humidity, concentration, or manner that replacement air or gas is

Vent, used in system names, does not not 1-7 Amendment No.159 I

Not Used

s.o DESIGN FEATURES 5-.l SITE EXCLUSION AREA 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, relnforc: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 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.

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--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

• • t*;

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 Progr1111.

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

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 el1111encs:

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.

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.

Sl Determination of CWllllative 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 members of the public unrestricted areas member of the public

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,

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,

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,

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,

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:

SALEM - UNIT 2 6-19b Amendment No. 320 site boundary member of the public site boundary site boundary LAR S21-04 LR-N21-0065 LAR H21-06 Mark-up of the Current Hope Creek Generating Station Technical Specification Pages The following Technical Specifications pages for Renewed Facility Operating License NPF-57 are affected by this change request:

Technical Specification Page INDEX i

INDEX ii INDEX iii INDEX xxiii DEFINITIONS 1-4 DEFINITIONS 1-7 DEFINITIONS 1-9 5.0 5-1 Figure 5.1.1-1 5-2 Figure 5.1.2-1 5-3 6.8.4.g 6-16b 6.8.4.g 6-16c 6.8.4.g/h 6-16d 1

1. 0 DEFINITIONS

• PAGE 1.1 ACTION

• 1-1 1. 2 DELETED

• 1-1 1.3 AVERAGE PLANAR LINEAR HEAT GENERATION RATE.

1-1

1. 4 CHANNEL CALIBRATION.*

1-1

1. 5 CHANNEL CHECK

• 1-1

1. 6 CHANNEL FUNCTIONAL TEST.

1-1 1.7 CORE ALTERATION

• 1-2

1. 8 DELETED

• 1-2

1. 9 CORE OPERATING LIMITS REPORT

• 1-2 1.10 CRITICAL POWER RATIO

• 1-2 1.11 DOSE EQUIVALENT I-131

• 1-2 1.11.1 DRAIN TIME

• 1-2a 1.12 E-AVERAGE D ISINTEGRATION ENERGY

• l-2a 1.13 EMERGENCY CORE COOLING SYSTEM (ECCS)

RESPONSE TIME.

1-3 1.14 END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME

• 1-3 1.15 DELETED

• 1-3 1.16 DELETED

• 1-3 1.17 FREQUENCY NOTATION *

• 1-3 1.18 IDENT IFIED LEAKAGE

• 1-3 1.18.1 INSERVICE TESTING PROGRAM.

1-3 1.19 ISOLATION SYSTEM RESPONSE TIME

• 1-3 1.20 L IMITING CONTROL ROD PATTERN

• 1-3

1. 21 LINEAR HEAT GENERATION RATE

• 1-4 1.22 LOGIC SYSTEM FUNCTIONAL TEST

• 1-4 1.23 DELETED.

1-4 1.24 MEMBER(S)

OF THE PUBLIC.

1-4 1.25 M IN IMUM CRITICAL POWER RATIO

• 1-4 HOPE CREEK i

Amendment No.

213 Not Used

DEFINITIONS SECTION DEFINITIONS (Continued)

PAGE 1.26 OFF-GAS RADWASTE TREATMENT SYSTEM

.................................................................. 1-4 1.27 OFFSITE DOSE CALCULATION MANUAL......................................................................... 1-4 1.28 OPERABLE-OPERABILITY................................................................................................. 1-5 1.29 OPERATIONAL CONDITION - CONDITION........................................................................ 1-5 1.30 PHYSICS TESTS.................................................................................................................. 1-5 1.30-1 PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR).......................................... 1-5 1.31 PRESSURE BOUNDARY LEAKAGE................................................................................... 1-5 1.32 PRIMARY CONTAINMENT INTEGRITY.............................................................................. 1-5 1.33 PROCESS CONTROL PROGRAM...................................................................................... 1-6 1.34 PURGE-PURGING............................................................................................................... 1-6 1.35 RATED THERMAL POWER................................................................................................. 1-6 1.36 REACTOR PROTECTION SYSTEM RESPONSE TIME..................................................... 1-6 1.37 REPORTABLE EVENT

......................................................................................................... 1-6 1.38 ROD DENSITY..................................................................................................................... 1-6 1.39 SECONDARY CONTAINMENT INTEGRITY....................................................................... 1-7 1.40 SHUTDOWN MARGIN......................................................................................................... 1-7 1.41 SITE BOUNDARY................................................................................................................. 1-7 1.42 Not Used............................................................................................................................... 1-8 1.43 SOURCE CHECK................................................................................................................. 1-8 1.44 SPIRAL RELOAD................................................................................................................. 1-8 1.45 SPIRAL UNLOAD................................................................................................................. 1-8 1.46 STAGGERED TEST BASIS................................................................................................. 1-8 1.47 THERMAL POWER.............................................................................................................. 1-8 1.48 TURBINE BYPASS SYSTEM RESPONSE TIME................................................................ 1-9 HOPE CREEK ii Amendment No. 209 Not Used

INDEX DEFINITIONS SECTION DEFINITIONS (Continued) PAGE 1.49 UNIDENTIFIED LEAKAGE....................................... 1-9 1.50 UNRESTRICTED AREA.......................................... 1-9 1.51 VENTILATION EXHAUST TREATMENT SYSTEM....................... 1-9 1.52 VENTING..................................................... 1-9 TABLE 1.1, SURVEILLANCE FREQUENCY NOTATION....................... 1-10 TABLE 1.2, OPERATIONAL CONDITIONS............................... 1-11 HOPE CREEK iii Amendment No. 34 Not Used

INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE Exclusion Area and Map Defining Unrestricted Area and Site Boundary for Radioactive Gaseous and Liquid Effluents............................5-1 Figure 5.1.1 1 Exclusion Area and Unrestricted Areas and Site Boundary for Radioactive Gaseous and Liquid Effluents........................................................5-2 Low Population Zone..................................................................................5-1 Figure 5.1.2 1 Low Population Zone................................................5-3 5.2 CONTAINMENT Configuration..............................................................................................5-1 Design Temperature and Pressure.............................................................5-1 Secondary Containment.............................................................................5-1 5.3 REACTOR CORE Fuel Assemblies.........................................................................................5-4 Control Rod Assemblies.............................................................................5-4 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature.............................................................5-4 Volume.......................................................................................................5-5 5.5 METEOROLOGICAL TOWER LOCATION...........................................................5-5 5.6 FUEL STORAGE Criticality.....................................................................................................5-5 Drainage.....................................................................................................5-5 Capacity.....................................................................................................5-5 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT...................................................5-5 Table 5.7.1 1 Component Cyclic or Transient Limits.......................5-6 HOPE CREEK xxiii Amendment No. 184 Site Location....................................................................................5-1

DEFINITIONS LIMITING CONTROL ROD PATTERN 1.20 A LIMITING CONTROL ROD PATTERN shall be a pattern which results in the core being on a thermal hydraulic limit, i.e.,

operating on a limiting value for APLHGR,

LHGR, or MCPR.

LINEAR HEAT GENERATION RATE 1.21 LINEAR HEAT GENERATION RATE (LHGR) shall be the heat generation per unit length of fuel rod.

It is the integral of the heat flux over the heat transfer area associated with the unit length.

LOGIC SYSTEM FUNCTIONAL TEST 1.22 A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all logic components, i.e.,

all relays and contacts, all trip units, solid state logic

elements, etc, of a logic circuit, from sensor through and including the actuated device, to verify OPERABILITY.

The LOGIC SYSTEM FUNCTIONAL TEST may be performed by any series of sequential, overlapping or total system steps such that the entire logic system is tested.

1.23 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.

MINIMUM CRITICAL POWER RATIO 1.25 The MINIMUM CRITICAL POWER RATIO (MCPR) shall be the smallest CPR which exists in the core.

OFF-GAS RADWASTE TREATMENT SYSTEM 1.26 An OFF-GAS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting reactor coolant system off gases from the main condenser evacuation system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

OFFSITE DOSE CALCULATION MANUAL 1.27 The OFFSITE DOSE CALCULATIONAL MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program.

The ODCM shall also contain

{1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating Report and the Annual Radioactive Effluent Release Report required by Specifications 6.9.1.6 and 6.9.1.7.

HOPE CREEK 1-4 Amendment No.163 Not Used

DEFINITIONS SECONDARY CONTAINMENT INTEGRITY 1.39 SECONDARY CONTAINMENT INTEGRITY shall exist when:

a.

All secondary containment penetrations required to be closed during accident conditions are either:

1.

Capable of being closed by an OPERABLE secondary containment automatic isolation system, or

2.

Closed by at least one manual valve, blind flange, or deactivated automatic valve or damper, as applicable secured in its closed position, except as provided in Table 3.6.5.2-1 of Specification 3.6.5.2.

b.

All secondary containment hatches and blowout panels are closed and sealed.

c.

The filtration, recirculation and ventilation system is in compliance with the requirements of Specification 3.6.5.3.

• d.

For double door arrangements, at least one door in each access to the secondary containment is closed, except when the access opening is being used for entry and exit.

e.

For single door arrangements, the door in each access to the secondary containment is closed, except for normal entry and exit.

f.

The sealing mechanism associated with each secondary containment penetration, e.g.,

welds, bellows or 0-rings, is OPERABLE.

g.

The pressure within the secondary containment is less than or equal to the value required by Specification 4.6.5.1.a, except as indicted by the footnote for Specification 4.6.5.1.a SHUTDOWN MARGIN (SOM) 1.40 SOM shall be the amount of reactivity by which the reactor is subcritical or would be subcritical throughout the operating cycle assuming that

a.

The reactor is xenon free;

b.

The moderator temperature is<: 68°F, corresponding to the most reactive state; and

c.

All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn. With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.

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.

HOPE CREEK 1-7 Amendment No. 218 Not Used

DEFINITIONS TURBINE BYPASS SYSTEM RESPONSE TIME 1.48 The TURBINE BYPASS SYSTEM RESPONSE TIME*consists of two separate time inter vals:

a) time from initial movement of the main turbine stop valve or con trol valve until 80% of the turbine bypass capacity is established, and b) the time from initial movement of the main turbine s top valve or control valve until initial movement of the turb ine bypass valve.

Either response time may be measured by any series'of sequential, overlapping, or total steps such that the ent i re response time is measured.

UNIDENTIFIED LEAKAGE 1.49 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENT.IFIED LEAKAGE.

UNRESTRICTED AREA 1.50 An UNRESTRICTED AREA sha ll be any area at or beyond the SITE BOUNDARY access to which is not control l ed by the licensee for purposes of protec tion of i nd ividuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

VENTILATION EXHAUST TREATMENT SYSTEM 1.51 A VENTILATION E'HAUST TREATMENT SYSTEM shall be any system desjgned and installed to reduce gaseous radioiodine or radioactive mater i al in particuM late form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from*the gaseous ekhaust stream prior to the release to the environment.

Such a system is not considered to have any effect on noble gas effluents.

Engineered Safety Feature (ESF) atmospheric cleanup systems are not consi dered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

VENTING 1.52 VENTING shall be the contro ll ed process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition,

in such a manner that replacement air or gas is not provided or required during VENTING.

Vent, used in system names, does not i mp l y a VENTING process.

HOPE CREEK Amendment No.34 Not Used

5.. 0 DESIGN FEATURES 5.1 SITE EXCLUSION AREA AND MAP DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS 5.1.1 The exclusion area shall be as shown in Figure 5.1.1-1. Information regarding radioactive gaseous and liquid effluents which will allow identification of structures and release points as well as definition of UNRESTRICTED AREAS within the SITE BOUNDARY that are accessible to MEMBERS OF THE PUBLIC, shall be as shown in Figure 5.1.1-1.

LOW POPULATION ZONE 5.1.2 The low population zone shall be as shown in Figure 5.1.2-1.

The circle with the five mile radius is the low population zone.

5.2 CONTAINMENT CONFIGURATION 5.2.l The primary containment is a steel structure composed of a spherical lower portion, a cylindrical middle portion, and a hemispherical top head which form a drywell. The drywell is attached to the suppression chamber through a series of downcomer vents.

The suppression chamber is a steel pressure vessel in the shape of a torus. The drywell has a nominal free air volume of 169,000 cubic feet. The suppression chamber has an air volume of 137,000 cubic feet and a water region as described in Technical Specification Bases 3/4.6.2, Depressurization Systems.

DESIGN TEMPERATURE AND PRESSURE 5.2.2 The primary containment is designed and shall be maintained for:

a.

Maximum internal pressure 62 psig.

b.

Maximum internal temperature:

drywell 340°F.

suppression pool 310°F.

c.

Maximum external differential pressure 3 psid.

SECONDARY CONTAINMENT 5.2.3 The secondary containment consists of the Reactor Building, and a portion of the main steam tunnel and has a free volume of 4,000,000 cubic feet.

HOPE CREEK 5-1 Amendment No. 110 Replace with:

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.

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LOW POPULATION ZONE FIGURE 5.1.2-1 5-3 Intentionally Left Blank

6.8.4.f 6.8.4.g Primary Containment Leakage Rate Testing Program A program shall be established, implemented, and maintained to comply with the leakage rate testing of the containment as required by 10CFR50.54(o) and 10CFR50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in NEI 94-01, "Industry Guideline for Implementing Performance-Based Option of 1 O CFR 50 Appendix J," Revision 3-A, dated July 2012, and the conditions and limitations specified in NEI 94-01, Revision 2-A, dated October 2008.

The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 50.6 psig.

The maximum allowable primary containment leakage rate, La, at Pa, shall be 0.5% of primary containment air weight per day.

Leakage Rate Acceptance Criteria are:

a.

Primary containment leakage rate acceptance criterion is less than or equal to 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are less than or equal to 0.6 La for Type B and Type C tests and less than or equal to 0. 75 La for Type A tests;

b.

Air lock testing acceptance criteria are:

1)

Overall air lock leakage rate is less than or equal to 0.05 La when tested at greater than or equal to Pa,

2)

Door seal leakage rate less than or equal to 5 scf per hour when the gap between the door seals is pressurized to greater than or equal to 10.0 psig.

The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage Rate Testing Program.

The provisions of Specification 4.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.

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 MEMBER{S) 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:

HOPE CREEK 6-16b Amendment No. 207 member(s) of the public

ADM I N I S T RAT IVE CONTROL S PROC E DU RE S AND P ROGRAMS

( Co nt i nued )

HOPE C REEK l)

Limitations on the operability of radioactive liquid and gaseous moni toring instrumentation including surve i l l ance tests and setpoint det erminat ion in accordance with the methodology in the ODCM,

2 ) Limitations on the concentrat ion o f radioact ive material released in l i quid e f f luents to UNRESTRICTED AREAS conforming to 1 0 CFR Part 2 0,

Appendix B, Table I I,

Column 2,

3 ) Monitoring,

sampl ing,

and analys i s o f radioact ive l iquid and gaseous e f f l uents in accordance with 10 CFR 2 0. 1 06 and with the methodology and parameters in the ODCM,

4 ) Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC f rom radioactive materials in l iquid e f fluents released f rom the unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 5 0,

5 ) Determination o f cumulat ive and proj ected dose contributions f rom radioactive e f fluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at l east every 3 1 days,

6 ) Limitat ions on the operability and use of the l iquid and gaseous effluent treatment systems to ensure that the appropriate port i ons o f these systems are used to reduce releases of radioact ivity when the proj ected doses in a 3 1 - day period would exceed 2 percent of the guidel ines for the annual dose or dos e commitment conforming to Appendix I to 10 CFR Part s o,

7 ) Limi tat ions on the dose rate resul ting from radioac tive material released in gaseous e f f luents to areas beyond the SITE BOUNDARY conforming to the doses associated with 1 0 CFR Part 2 0, Appendix B,

Table I I, Column 1,

6 - 1 6 c Ame n dme n t N o.

1 2 1 unrestricted areas member of the public unrestricted areas site boundary

ADMI N I STRAT I VE CONTROLS P ROCEDURES AND PROGRAMS

( Cont inued )

6. 8. 4. g.

I Radioactive Effluent Control s P rogram B ) Limitations on the annual and quarterly air doses result ing from noble gases released in gaseous effluents from the uni t t o areas beyond the S ITE BOUNDARY conforming t o Appendix I to 10 CFR Part 5 0,

9 ) Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC f rom Iodine - 13 1, Iodine - 1 3 3,

tritium,

and all radionuclides in particulate form with hal f - l ives greater than B days in gaseous effluents released from the unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part S O,

l O ) Limitations on venting and purging of the containment through the Reactor Building Venti lation System, Hardened Torus Vent,

or the FRVS to maintain releases as low as reaspnably achievable, and ll ) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioact ivi ty and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 1 9 0.

h.

Radiological Environmental Monitoring Program A program shall be provided to monitor the radiation and radionuclide s in the environs of the plant.

The program shall provide ( l ) representat ive measurement s of radioact ivity in the highes t potential exposure pathways,

and ( 2 ) veri ficat ion of the accuracy of the effluents monitoring program and modeling of the environmental exposure pathways.

The program shall

( 1 ) be contained in the ODCM,

(2 )

conform to the guidance of Appendix I to 1 0 CFR Part S O,

and

( 3 ) include the fol lowing :

HOPE CREEK 1 ) Monitoring, sampling,

analysis,

and reporting o f radiat ion and radionucl ides in the environment in accordance with the methodology and parameters in the ODCM,

2 ) A Land Use Census to ensure that changes in the use of areas at and beyond the S ITE BOUNDARY are identified and that modi ficat ions to the monitoring program are made if required by the resul ts of thi s census,

and 3 ) Part icipat ion in an Interlaboratory Comparison Program to ensure that independent checks on the precis ion and accuracy of the *measurements of radioact ive materials in environmental sample matri ces are performed as part of the qual i ty assurance program for environmental monitoring.

6 - 1 6d Amendment No.

1 2 1 site boundary member of the public member of the public site boundary LAR S21-04 LR-N21-0065 LAR H21-06 Mark-up of the Current Salem Unit 1 and Unit 2 Technical Specification Bases Pages for Information Only Salem Unit 1 Technical Specification Bases Page 3/4.3.3.8 B 3/4 3-3 3/4.11.1 B 3/4 11-3 Salem Unit 2 Technical Specification Bases Page 3/4.3.3.8 B 3/4 3-3a 3/4.11.1 B 3/4 11-3

BASES 3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room. This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.

3/4.3.3.6 THIS SECTION DELETED 3/4.3.3.7 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the Recommendations of Regulatory Guide 1.97, "Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1975.

The Wide Range Neutron Flux Monitors are the Gamma-Metrics Post-Accident Neutron Monitors.

3/4.3.3.8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The purpose of tank level indicating devices is to assure the detection and control of leaks that if not controlled could potentially result in the transport of radioactive materials to UNRESTRICTED AREAS.

3/4.3.3.9 THIS SECTION DELETED 3/4.3.3.10 THIS SECTION DELETED 3/4.3.3.11 THIS SECTION DELETED 3/4.3.3.12 THIS SECTION DELETED 3/4.3.3.13 THIS SECTION DELETED SALEM - UNIT 1 B 3/4 3-3 Amendment No. 320 (PSEG Issued) unrestricted areas

RADIOACTIVE EFFLUENTS BASES Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an ycontrolled release of the tanks '

contents, the resulting concentrations would be less than the limits of 10 CFR Part 2 0, Appendix B, Table I I, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

3/4. ll. 2 GASEOUS EFFLUENTS 3 /4. ll. 2. l Deleted SALEM -

UNIT l B 3/4 ll-3 Amendment No. 234 unrestricted area

INSTRUMENTATION BASES 3/4.3.3.8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The purpose of tank level indicating devices is to assure the detection and control of leaks that if not controlled could potentially result in the transport of radioactive materials to UNRESTRICTED AREAS.

3/4.3.3.9 THIS SECTION DELETED 3/4.3.3.10 THIS SECTION DELETED 3/4.3.3.11 THIS SECTION DELETED 3/4.3.3.12 THIS SECTION DELETED 3/4.3.3.13 THIS SECTION DELETED SALEM - UNIT 2 B 3/4 3-3a Amendment No. 265 (PSEG Issued) unrestricted areas

RADIOACTIVE EFFLUENTS BASES Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks '

contents,

the resulting concentrations would be less than the limits of 1 0 CFR Part 2 0, Appendix B, Table I I, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

3/4. ll. 2 GASEOUS EFFLUENTS 3 /4. ll. 2. l Deleted SALEM UNIT 2 B 3/4 11*3 Amendment No. 215 unrestricted area LAR S21-04 LR-N21-0065 LAR H21-06 Mark-up of the Current Hope Creek Technical Specification Bases Pages for Information Only Technical Specification Bases Page 3/4.11.1.4 B 3/4 11-1

3 / 4. 1 1 RAD I OACT I VE E c fLUENTS BAS E S 3 / 4. 1 1. 1 De l e t ed 3 /4. 1 1. 1. 2 Del e ted 3 / 4. 1 1. 1. 3 De l eted 3 /4. 1 1. l. 4 L IQUID HOLDUP TANKS The tanks l i s ted in this speci f ication include a l l those outdoor radwaste tanks that are not surrounded by l iners,

dike s,

or wal l s capable o f holding the tank contents and that do not have tank over f l ows and surrounding area drains connected to the Liquid Radwaste Treatment Sys tem.

Re s t r i c t ing the quant ity o f radioact ive mat erial contained in the speci f i ed t anks provides assurance that in the event of an uncontro l l e d re lease of the tanks '

cont ents, the re sul ting concent rat ions woul d be l e s s than the l imits of 1 0 CFR Part 2 0, Appendix B,

Table I I,

Col umn 2, at the neare s t pot ab l e water supply and the neare st surface wat er s uppl y in an UNRESTR ICTED AREA.

3 /4. 1 1. 2 GASEOUS EFFLUENTS 3 /4. 1 1. 2. 1 Deleted 3 / 4. 1 1. 2. 2 Deleted 3 /4. 1 1. 2. 3 De l e ted 3 / 4. 1 1. 2. 4 Dele ted 3 /4. 1 1. 2. 5 Del e t ed 3 / 4. 1 1. 2. 6 De leted 3 / 4. 1 1. 2. 7 MAIN CONDENSER R e s t r i c t ing the gro s s radioactivity rate of nob l e gases f rom the ma in condenser provides reasonable assurance that the total body exposure to an individual at the excl us ion area boundary wi l l not exceed a small fract ion o f t he l imits o f 1 0 CFR Part 1 0 0 i n the event this e f f l uent i s inadvertently d i s charged d i re c t l y to the envi ronment without t rea tment.

Thi s spec i f i ca t i on imp l ement s the requi rement s of General Des ign Crite ria 6 0 and 6 4 o f Appendix A to 1 0 CFR Part 5 0.

H O P E CREEK B 3 / 4 1 1 - 1 Amendmen t No.

1 2 1 unrestricted area