ML19044A574

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Supplement to Technical Specifications Proposed Change - Permanently Defueled Technical Specifications
ML19044A574
Person / Time
Site: Pilgrim
Issue date: 02/08/2019
From: Halter M
Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
2.19.007
Download: ML19044A574 (21)
v • d • e


Text

{{#Wiki_filter:Entergy Nuclear Operations, Inc. 1340 Echelon Parkway Jackson, MS 39213 Tel 601-368-5573 Mandy K. Halter Director, Nuclear Licensing 10 CFR50.90 2.19.007 February 8, 2019 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555

SUBJECT:

Supplement to Technical Specifications Proposed Change - Permanently Defueled Technical Specifications Pilgrim Nuclear Power Station Docket No. 50-293 Renewed License No. DPR-035

REFERENCES:

1. Letter, Entergy Nuclear Operations, Inc. to NRG, "Technical Specifications Proposed Change - Permanently Defueled Technical Specifications" dated September 13, 2018 (Letter Number: 2.18.034) (ML18260A085)
2. Letter, Entergy Nuclear Operations, Inc.to NRG, "Application for Order Consenting to Direct and Indirect Transfers of Control of Licenses and Approving Conforming License Amendment; and Request for Exemption from 10 CFR 50.82(a)(8)(i)(A)" dated November 16, 2018 (Letter Number 2.18.067) (ML18320A031)

Dear Sir or Madam:

In accordance with Title 1O Code of Federal Regulations (CFR) 50.90, Entergy Nuclear Operations, Inc. (Entergy) proposed an amendment to Renewed Facility Operating License (OL) DPR-35 for Pilgrim Nuclear Power Station (PNPS). This proposed license amendment revised the OL and the associated Technical Specifications (TS) to Permanently Defueled Technical Specifications (POTS) consistent with the permanent cessation of reactor operation and permanent defueling of the reactor (Reference 1). In Reference 2, Entergy submitted an Application for Order Consenting to Direct and Indirect Transfers, of Control of Licenses and Approving Conforming License Amendment to Holtec Decommissioning International and Holtec Pilgrim LLC. The purpose of this letter is to update the OL and associated TS to reflect the proposed change in ownership from Entergy Nuclear Generation Company and Entergy to Holtec Decommissioning International and Holtec Pilgrim LLC. The administrative changes are reflected in the attachments to this letter. In the event

Letter No. 2.19.007 Page 2 of 2 that Reference 2 is not approved by the U.S. Nuclear Regulatory Commission, then this Supplement will be withdrawn. Entergy has reviewed the administra~ive changes to the retyped pages and determined that the conclusion in the September 13, 2018 (Reference 1), letter that the proposed changes do not involve a significant hazards consideration is not changed. In accordance with 10 CFR 50.91, a copy of this application, with attachments, will be provided to the Commonwealth of Massachusetts. to this letter provides a markup of the changes to the OL and POTS. Attachment 2 contains the retyped OL and POTS pages reflecting the changes described above. There are no new regulatory commitments made in this letter. If you have any questions on this transmittal, please contact Mr. Peter J. Miner at (508) 830-7127. , I declare under penalty of perjury that the foregoing is true and correct. Executed on February 8, 2019 .. l/!7~ Sincerely, Mandy K. Halter MKH/rmc Attachments:

1. Markups of the Proposed Operating License and Permanently Defueled Technical Specifications
2. Retyped Operating License and Permanently Defueled Technical Specifications Pages cc: USNRC Regional Administrator, Region I USNRC Project Manager, Pilgrim USNRC Resident Inspector, Pilgrim Planning and Preparedness Section Chief, Massachusetts Emergency Management Agency Director, Massachusetts Department of Public Health, Radiation Control Program

Attachment 1 Letter Number 2.19.007 Markups of the Proposed Operating License and Permanently Defueled Technical Specifications

HOLTEC PILGRIM, LLC And HOLTEC DECOMMISSIONING INTERNATIONAL J/ ENTS.qGY N-YGkEAR-GENE-RATION COMPANY

  • AAe-E--N+EPi-9¥-N.YGbeAP..-GPeRA+!OJIJS,. ING.

{PILGRIM NUCLEAR POWER STATION) DOCKET NO. 50-293 RENEWED FACILITY BP-ePrA:1:1NG-UCENSE Renewed License No. DPR-35 The Nuclear Regulatory Commission (the Commission} has found that:

a. *l:lrocpt asi>tatcd ~n condition 6, eonstruetion of the Pilgri~Cf-StatieA-ftAe,
.------,..,* fliaeility) ha&boen e1:1estantially completed in conformity with the application, as amended.

jOEL.ETEO ~ tl=le-Provisional Construction Permit ~QP.49, the provtsiens of tt:le Atomic Energy Act of 1 9 ~(the Act), and the rules and regutatieAs of the GommissieA-aS set-fGl:tf=l..i.n Title 10, Chapter ~, CF-R;-aAG 

                                                              ---.be maintained
b. The facility will e ~ conformity with the application, as amended, the provisions of the Act, and the rules and regulations ~tr;Le..ld:llll!lll*~*aa;*~ig_,.--,-___,,,..,.,.__,.....,,..

Holtec Pilgrim; LLC {Holtec Pilgrim) C. There is reasonable assurance (i) t af e ac 1v1 1es au onze y e renewe operating license can be conducted withou endangering the health and safety of the public, and (ii) that such activities will the Commission; and 70 c ducted in compliance with the rules and regulations of

d. The Entergy Nuclear Geneffition Gempany-{Entergy-Nuclear) is financially qualified and
                 ~ u o l e a r O p ~ is echnically and financially qualified to engage in the activities authorized by this renewe o
  • icense, in accordance with the rules and regulations of the Commission; and !Hottec Decommissioning International (HDI)
                                                 ,;. - - - - !HDI I                      .
e. Effler~ and EN~lie satisfied the applicable provisions of 10 CFR Part 140, "Financial Pro Requirements and Indemnity Agreements" of the Commission's regulations; and Holtec Pilgrim
f. The issuance of this renewed operating license will not be inimical to the common defense and security or to the health and safety of the public; and
g. After weighing the environmental, economic, technical, and other benefits of the facility against environmental costs and considering available alternatives, the issuance of this renewed opel'atiA§-license (subject to the condition for protection of the environment set forth herein) is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements of said regulations have been s a t i s f i e d ~

h.0"~tions halfe been id,ep,tified and fclalfe been or will be tal<en with rcspeetto (1) FAanagifl§, 

            . the effects of aging during the period of extended operation on the funetionailly-e#

!DELETED structures and COffil:lOAcnts that Aa 11e eceA identifies to require review uAder

!~uelear Regulatory Gommissio~U:ie transfer of the license from Boston Edison G o ~

to EAtergy Nuclear G e n e r a t i o ~ r i l 29, 1999. 

              !Amendment No. XXX

4e-GF.q. 64.21 (a.)(1 ); and (2) time limtted aging analyses that hONe been identified to requiFC review*tffider 10 GFR-54.21(0), such thattherc is reasonable assurance thatthe aetivitics auth~-eAeWcd operating license wttl-ceffiim:te.1:-e-be eenduoted iA-aseordanse with tho eurrent l i s e n s i ~ ~ ~ and that any changes made to tho facility's current licensing basis in order to comply with 1O GFH-54.29(a) arc in accordance wtth-U1c Act and the Commission's regulations. Facility Operating License No. DPR-35, dated June 8, 1972, issued to the Boston Edison Company (Boston Edison) is hereby amended in its entirety, pursuant to an Initial Decision dated September 13, 1972, by the Atomic Safety and Licensing Board to read as follows: 

                                                                               . __ *. /    Holtec Pilgrim      ,
1. This renewed eperating license applies to the Pilgr~~1car Power Station, single cycle, forced circulation, boiling water nuclear ~ o r and associated electric f{nerating equipment (the facility), owned by Entergy N ~ and~eratcd by Ef>JG.. The...~cility is located on the western shore of Cape Cod Bay in the t "'n of Plymouth 0"'1 e ~

Ntlel-eaf.site in Plymouth County, Massachusetts, and is scribed in the "Fin Safety Analysis Report," as supplemented and amended. maintained HDI Holtec Pilqrim

2. Subject to the condition n requ ments incorporated herein, the Commission hereby licenses Eftt~ti and A. Pursuant to the S tion 104b of the Atomic Energy Act of 195 , as amended (the Act) and 10 C6 Part 50, "licensing of Production and Utiliz *on Facilities," a)
                              ~ l e a r t o possess and use and b) EN~possess;'Use, and operate
  ...th_t____d__, the facility as a utili2ation faeimy at the designate                    ation on the Pilgrim site; a was use                                                                               jHDI I r;-;;:::-;i B~ENG; pursuan                      ct and 10 CFR 70, to receive, possess~at any
         ~                    time special nuclear maten         s reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final that were used                 Safety Analysis Report, as supplemented and amended;                       calibration of
           .....--. C ~ ' , ursuant to the Act and 10 CFR Parts 30, 40 and 70 o receive, possess
           ~                  and use ~y time any byproduct, source or special n ear material as sealed neutron sour~ for reactor startup, sealed source or reactor instrumentation
                              ~~adiation monitoring equipment ealier-atieA-, and            fission detectors in
       ~ - -7 rnvunts as required;                                   ,                           that were used D.       ENG-, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and E.       ENG-, pursuant to the Act and 10CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
3. This renewed e~tifl§-license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations; 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50 and Section 70.32 of 10 CFR Part 70; and is subject to all applicable
                     !Amendment No. XXX        I                                         Renewed License No. DPR-35

provisions of the Act and lo the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below: A. ~-eweF-1:ae vel ( !DELETED I ENO is a~e-tRe- fa61lity at steaely-s-tat&fJeweF-levels not to 2028 

             ~ed             me~###                            replaced with the Permanently Defueled B.      Technical Specifications                          Technical Specifications The Technical Speci         tions contgi1 ed in Appendix A, as revised through Amendment No.           , are hereby fffcorporated in-t~.1e9-8!3e ratin9 license. I The licensee shall Gperate the facility in accordance with the Technical Specifications.        ~                                          ~

C. Records m a i n t a i n P e r m a n e n t l y Defueled I 

 !HDI !~--00 shall keep facility Gj38fatin~ecords in accordance with the requirements of the Technical Specifications.

D. §qualrae~ GtieA- DELETED E. RsGifsulat-ioo-beee-l-Aooer:able- DELETED F. Fi~GA tjDELETED I E..NG-sl: !all-im~in in effect all pmvisi9FIS-G f-tl:le-a~ J3f8leGti8A-f1Fe§ram as dSSGfieeEl-if l-tl=le-F-iRa~e par:t-feF-the fuility-a1*i-a& -apJ3FGVeEH ~G-9ecemeer 21, 1978 as SYf!Plemented slalbject to the follewiR9-t>F9'Ji.sleffi 

            ~~~e~FIGF
            ~~~hange s-wGYkJ- Rol-advei :sely-afres t-too ability to achie*1e and maintain safe shutdowA-in the event of a fire.

G. Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Pilgrim Nuclear Power Station Physical Security, Training and Qualification, and Safeguards Contingency Plan, Revision O" submitted by letter dated October 13, 2004, as supplemented by letter dated May 15, 2006. The licensee shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The licensee's CSP was approved by License Amendment No. 236, as supplemented by changes approved by Amendment Nos. 238,241,244, and 247. Amendment No.Im! Renewed License No. DPR-35

!DELETED ~ *4* H. *est Aee;aeat Samplh,o Sysleffi. NYREG G737 llem 11.B.a. aaa Gentainfficnt Atmesphcric Monitoring Svstcm, NUREG 0737. Item 11.F,*H§t The licensee shall coFAplete the installation of a post accident sampling system and a containment atmospheric monitoring system as soon as practicable, but no later than June 30, 198&.- ~ I. Additional Conditions 

                    ~al-GoAeitions contained in Appendtx-B;-as Fevised through Amendment Ne. 177, are heFOby incorporated into this renewed operatin§-

license. ENO shall operate the facility in accordance with the Additional Conditions. J. Conditions Related to the Sale and Transfer 

                              ~            Nuclear sl'lall provide a Provisional Trust funt:l in tl'le amot:lffl-ef
                              $70 FAil!ien, af.ter payfflent of any taxes, in the ~-ienal =FFust for Pil§rim upon the transfer of tl'le Pilgrim licenses-to-Entergy Nuclear. The Delet~d t.e.----:;,-t-P'AF03'\fll 1iS:H<iOetA'li:aH-l-tTflFU:fl:Srt-t51ShAia:l 1111-1;b:1<:CHe:*Smta:t1:bt t1iS1ShCN:Of idHa:t n'ldHmitaaiitflntctat11inCN:ef idHirtn-GCi60ffinfreOlf FFAf!iaa1n'lteree w ~ a t i o n s rnade-ift-tA~13lieatioo-fer-a-19f:3roval of ti'le transfer.

Entergy Nuclear shall have access to a contingency f1,md of not less than 

                               *       * *en dollaFS ($Wm-) for payment, if needed, of PilgriA'l operating ood maintenance expenses, the cost to transition to decoA'lmiss-io-l'ltA§'

status in the event of a decision to permanently shut down the unit, and-t'le!Elffiffi!SSief1tA0~rt&:-~tel'0~clel~IVli*IHai~-AeeeSSaf'f-S~ ensuFO tl'lat access to these funds-will remain available until the full amount has been e x ~ r p o s e s described above. Entergy Nl:telear-sAall-iffiefm the Director, Office of Nuclear Re§ulation, in writing, at-suoh time that it utilizes any of these contingeney-R:ff'lds. Tl'lis pFOvision docs not affect the NRG's authority to assure that adequate funds-will remain available in the plant's separate decommissioning fund(s), wl'lieh Entergy Nuclear sl=lall maintain in accordance with NRG regulations. Once the plant has been plaeed in a safe shutdewn condition followif!§-& deeision to decOfRRlission, Entergy Nuclear will use any rernainder-ef-the- 

                              $50m contingency fund that has not been used to safely operate and maintain the plant to support the safe and pFOmpt deeoA'lmissioning of the plant, to the e~ent such funds are needed for srae and prompt decommissioning.
                            !Amendment XXX                   I                                                                    Renewed License No. DPR-35

(5) The Decommissioning Trust agreement(s) shall be in a form which is acceptable to the NRC and shall provide, in addition to any other clauses, that: a) Investments in the securities or other obligations of Entergy Nuclear, Entergy Gorporatie-A-, their affiliates, subsidiaries or associates, or their successors or assigns Holtec Pilgrim, Holtec shall be prohibited. In addition, except for investments tied Decommissioning to market indexes or other non-nuclear sector mutual International funds, investments in any entity owning one or more nuclear power plants is prohibited. b) The Director, Office of Nuclear Reactor Regulation, shall be given 30 days prior written notice of any material amendment to the trust agreement{s). K. Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas: (a) Fire fighting response strategy with the following elements:

1. Pre-defined coordinated fire response strategy and guidance
2. Assessment of mutual aid fire fighting assets
3. Designated staging areas for equipment and materials
4. Command and control
5. Training of response personnel (b) Operations to mitigate fuel damage considering the following:
1. Protection and use of personnel assets
2. Communications
3. Minimizing fire spread
4. Procedures for implementing integrated fire response strategy
5. Identification of readily-available pre-staged equipment
6. Training on integrated fire response strategy
7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of:
1. Water spray scrubbing
2. Dose to onsite responders L. The licensee shall implement and maintain all Actions required by Attachment 2 to NRC Order EA-06-137, issued June 20, 2006, except the last action that

~ requires incorporation of the strategies into the site security plan, contingency 

   * * \ plan, emergency plan and/or guard training and qualification plan, as appropriate.

M. tlpon Implementation ef AmenElment Ne. 231 a e l e ~ 

           ~ - e ~ ~ - G R E ~ unfilteree-aif-iflleaka§ required by SP.-4.7.S.2.c in aecorelanec v.,'l1'tl=!-=F&&:>-:&&.fl'fl.:-tre-asSE*iSflW-Flt-ef
  • ORE t:iabitability as required by Speonicatien 5 . ~ . and tt:ic measurement Renewed License No. DPR-35
         !Amendment XXX      I

                                                          . 6.

ef-GRE pressure as required sy-Sj3effieati8fl~~:e-ErAatl-9e-e~~:Jre0-fl'let-a& f.ellews+ (a) The first performance of S R ~ . e in accordance with Speeif-ieatioa 

                         §.:£.8.c.(i) shall be within tl=le specified frequency of 6 years, plus the 18-month allowance as defined by-SY-.~                                        , ed from 9ccomber-&,-2005, the dat-0 of the most FCoent-suoccssful tracer gas test, as statee-iA-Entorgy's letter " F o l l o v - ~ ~ e r i e Lctter-2800-
                         ~19-2:Gf3.019), datce Mafoh 20, 209~months if the time 13vo-fio~reoent successful tracer gas test is greater than 6 year:&:

(b) The first performance of the periodic assessment of GRE habitabi#ty-Spocification 5-:&:8.o.(ii) shall be WffAifl a years, plus-the 9 month allowaAee ef-SIJPNEILLANG&1NTEP.¥AL as measured from Deoefflaef-5,2995;--#le-date of the most recent Sl:lGcssfu1 tmeer gas test, as states in Entef§y's* 

                         ~ . e s j 3 o n s e to NRG Generic !.:otter 200a 01" ( E N ~ ~

da~OS,or-within 9 months if the time perioa-siAce the mos~ recent successful tracer gas test is greateHl'laA3 yeaf&.- (e) The first performance of the periodic measurement of CPS-pressure, 

                         ~~~A 2 4 m o A t h s ; - p l H s ~
                         =R@

of the SURVEILLANCe-1-N+ERVAL as m c a s ~ a t c of tt:ic most IDELETED ~ ,eseol 5"'8ess!ul ~,essuFe R!easure"'eot tesl e<-wi!l!lo , BG Be~s ff REIi 4Ch~ llseose eeoBoleo le, lhe ~FE>leelieo ellhe e a o i - 13eeten-EfiiseA-Shall-eentinuc. for-a-J3criod of fi*,e years after in~f:}er-atien of the facility, an environmental monitoAAffl'0gram similar to that presently C } . . ~ GommoAWealth of Massaohusctts (and d c s c r i e C E l - § e A c ~ EE!ison's Environmental Report, Operating License-Stage eatcd September, 1970} as-a ~ b~~is for dct-Ofmi-Amg tt:ie _e}a()nt of stati?n iRfltiene&-efl-ffiarine rcS0ttF0es one shall 

   ~   ~ m1t1gatc aevcrsc effects, 1f any, on-manna resources.
5. Boston Edison has-Rot completed as yet construction of the Rae-Waste Solidification
         ~ " R e n t e d Off Gas System. Limiting eonditioAs-eeneeiru~

systems are set forth in tho Technical Specifications.

6. '/ ursuant to-Section 1066(8) of the Act, the Commission has ooASultee;vttltthe Attorney General regardiA§ the issuanee-of-this operating license. After--sai&

consultation, the Commission has dctermtncd tt:lat the issuance of this liccns;' subject to the conditions set forth in this s u b p ~ v a n c c of consideration of and findings witt:I respect to matters covered in SeetieA 105c of the Ast, is necessary in the puWio interest to avcie unnecessary eelay in the opcFOtion of the facility. Nf. the time tl'lis operating license is acing issued an antitfust f*eceeding ha&net been noticed. The Gommissiafl;-aeeerdingly, has made A& dctCFFnination with respect t-0 matters covered in Section 105e-ef-the Act, inelt:latt'r§' eeAEfilions, if any, which may be appropriat-0 as a result of the eutcome of any antitrust proceeding. On the basis ef its findings made as-a-result of an antitrus~ proceeding, the Commission Fnay continue this liecnsc as issueel, rescind this-lioense or amend this license to include suoh conditions as the Gommissien-Renewed License No. DPR-35

(looms appropriate. BesteA--Edison and others who may be affected hereey-are ooeerdin§ly on notioe that the §ranting of this lioens~s-witl=le~ efee to any subsequent licensing action;-iAoluding the im13osftieA-ef.-af3i3r-epriate conditiornr, 

            *,NRieh may be tal~mmissio n as a result oHl=le-euteome-of any antitrust proceeding. lf1 the eourse of its planning and other activities, Boston Eeisefl-WH!-ee.

expoeted to eenduct itself accordingly.

7. The information in the FSAR supplement, submitted pursuant to 10 CFR 54.21 (d}, as supplemented by Commitments Nos. 3, 8, 9, 13, 15, 18, 19, 21, 22, 24, 25, 26, 27, 28, 30, 31, 33, 34, 35, 36, 37, 39, 40, 46, 51, and 52 of Appendix A of NUAEG-1891, "Safety Evaluation Report Related to the License Renewal of Pilgrim Nuclear Power Station" dated June 2007, as supplemented, is henceforth part of the FSAR which will be updated in accordance with 1o CFR 50. 71 (e}. In addition, the licensee shall incorporate into its F~escription of Program" from Table a.o 1 "FSAR Supplcmcffi-fer:

A - § ~ f Applicable Systems" of bioense RenmNal-lAter-tm-Staff Guidanee-1 : : P ~ § e i n g Review of Operating E - ~ The licensee may make changes to the programs and activities described in the FSAR supplement and Commitments Nos. 3, 8, 9, 13, 15, 18, 19, 21, 22, 24, 25, 26, 27, 28, 30, 31, 33, 34, 35, 36, 37, 39, 40, 46, 51, and 52 of Appendix A of NUREG-1891, as supplemented, provided the licensee evaluates such changes pursuant to the criteria set DELETED forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

8. pplement submitted pursuant to 1O GFP.-54.21 (d), as revise&

during the license renewal application review process-;-arul as supplemented by Commitments N ~ :t-6,4-8, 19, 21, 22, 24, 25, 26, 27, 28, ao, a1, aa. 34,a&,- a ~ ~ - A - e f - N l : l . . . ~ m e n t e d , alofltt wi-th the FSAR description regarding eonsieer-ation of opeFO:ting experiencc-ref-lieeRSe-reReiNal-ag<<'lg managemeRt pmgramo in Condition 7 abo>Je, aesefibcs certain future J*egr:ams and activities to ee corn13letea-eefare the 13eriod ~ ~ " r . - " F A e - lioensee shall complete these activities no later than June 8, 2012, and shall notify the 

!DELETED   NRG in writing when implementation of these astivities is complete.

1 9.6apsule withdFawal seh~enew ed operatiR§"lteeASe term, all capsttles-ifl-the reactor vessel tl=lat are removed and tested must meet the rcquireITTents-ef-Af'l'lefiean-S e e ~ a t e r i a l s (As:FM} 6-1-86 82 to the cxt<:nt praetieable-fer-tt-le- 

           ~ o n of the specimens in the capsule. Any e h a n g ~ - a w a J .

SSReal:00, including spare capsules, must be apprev-ee-by the staff prior to implemcntation,-Al ~ules-plaeed in storage m u ~ t t t r e - i f : l s e r t i Any shangcs to storage requirements must be approved by the staff; as required by 

           ~..J,,f.,..,

Renewed License No. DPR-35

until the Commission notifies the licensee in writing that the license is terminated

10. This license is effective as of the date of issuance a n d ~ ~ -

FOR THE NUCLEAR REGULATORY COMMISSION Original Signature on File Eric J. Leeds, Director Permanently Defueled Office of Nuclear Reactor Regulation Attachment : Appendix A - rechnical Specifications (Radiological) AJ313eA1tx-B--Af!Elitienal Gonelitiefls-Date of Issuance: May 29, 2012 

                           ~

Renewed License No. DPR-35

NOTE THAT THE FOLLOWING INCORPORATES AMENDMENT 246-ADMINISTRATIVE CHANGES DUE TO PERMANENT SHUTDOWN BECAUSE IT WILL BE IMPLEMENTED PRIOR TO THE IMPLEMENTATION DATE OF THIS AMENDMENT - THIS NOTE WILL NOT BE INCLUDED IN THE RETYPED TECHNICAL SPECIFICATIONS APPENDIX A PERMANENTLY DEFUELED TO FACILITY G.125-M='".-IN-S LICENSE DPR-35 ECHNICAL SPECIFICATIO~AND BASES FOR L@J PILGRIM NUCLEAR POWER STATION PLYMOUTH,MASSACHUSETTS 

              ~ ~ ~ o o d s.N+ER-G¥-m.~-A=R-9-.."JS,!N-S.

i jHoltec Pilgrim, LLC and Holtec Decommissioning International

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location !Holtec Pilgrim I Pilgrim Nuclear Power Station is located on thtestem shore of Cape Cod Bay in the Town of Plymouth, Plymouth County, MiJssachusetts and contains approximately 517 acres owned by E-ntergy-N1;1c~ear- as shown on FSAR Figures 2.2-1 and 2.2-2. The site boundary is posted and a perimeter security fence provides a distinct security boundary for the protected area of the station. The reactor (center line) is located approximately*1800 feet from the nearest property boundary. 4.2 

    ~

9eletee 4.3 

   ~Fuel Storage 4.3.1     Criticality 4.3.1.1     The spent fuel storage racks are designed and shall be maintained with:
a. Fuel assemblies having a maximum k-infinity of 1.32 for standard core geometry, calculated at the bumup of maximum bundle reactivity, and an average U-235 enrichment of 4.6 % averaged over the axial planar zone of highest average enrichment; and
b. Kett:. 0.9f? if fully flooded with unborated water, which includes an allowance for uncertainties as described in SeGti~of the FSAR.

the applicable section (continued) PNPS 4.0-1 Amendment No. 177, 1. 81, 24&

Attachment 2 Letter Number 2.19.007 Retyped Operating License and Permanently Defueled Technical Specifications Pages

HOLTEC PILGRIM, LLC And HOLTEC DECOMMISSIONING INTERNATIONAL (PILGRIM NUCLEAR POWER STATION) DOCKET NO. 50-293 RENEWED FACILITY LICENSE Renewed License No. DPR-35 The Nuclear Regulatory Commission (the Commission) has found that:

a. DELETED
b. The facility will be maintained in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; and
c. There is reasonable assurance (i) that the activities authorized by the renewed license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the rules and regulations of the Commission; and
d. Holtec Pilgrim, LLC (Holtec Pilgrim) is financially qualified and Holtec Decommissioning International (HDI) is technically and financially qualified to engage in the activities authorized by this renewed license, in accordance with the rules and regulations of the Commission; and
e. Holtec Pilgrim and HDI have satisfied the applicable provisions of 10 CFR Part 140, "Financial Protection Requirements and Indemnity Agreements" of the Commission's regulations; and
f. The issuance of this renewed license will not be inimical to the common defense and security or to the health and safety of the public; and
g. After weighing the environmental, economic, technical, and other benefits of the facility against environmental costs and considering available alternatives, the issuance of this renewed license (subject to the condition for protection of the environment set forth herein) is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements of said regulations have been satisfied.
h. DELETED Amendment No. ###

Facility Operating License No. DPR-35, dated June 8, 1972, issued to the Boston Edison Company (Boston Edison) is hereby amended in its entirety, pursuant to an Initial Decision dated September 13, 1972, by the Atomic Safety and Licensing Board, to read as follows:

1. This renewed license applies to the Pilgrim Nuclear Power Station, a single cycle, forced circulation, boiling water nuclear reactor and associated electric generating equipment (the facility), owned by Holtec Pilgrim and maintained by HDI. The facility is located on the western shore of Cape Cod Bay in the town of Plymouth on the Holtec Pilgrim site in Plymouth County, Massachusetts, and is described in the "Final Safety Analysis Report,"

as supplemented and amended.

2. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Holtec Pilgrim:

A. Pursuant to the Section 104b of the Atomic Energy Act of 1954, as amended (the Act) and 10 CFR Part 50, "Licensing of Production and Utilization Facilities," a) Holtec Pilgrim to possess and use and b) HDI to possess and use the facility at the designated location on the Pilgrim site; B. HDI, pursuant to the Act and 10 CFR 70, to possess at any time special nuclear material that was used as reactor fuel, in accordance with the limitations for . storage as described in the Final Safety Analysis Report, as supplemented and amended; C. HDI, pursuant to the Act and 10 CFR Parts 30, 40 and 70 to receive, possess

  • and use at any time any byproduct, source or special nuclear material as sealed neutron sources that were used for reactor startup, sealed sources that were used for calibration of reactor instrumentation and are used in radiation monitoring equipment, and as fission detectors in amounts as required; D. HDI, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and E. HDI, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
3. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations; 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50 and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:

A. DELETED Amendment No. ###

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. ###, are hereby replaced with the Permanently Defueled Technical Specifications. The licensee shall maintain the facility in accordance with the Permanently Defueled Technical Specifications. C. Records HPI shall keep facility records in accordance with the requirements of the Technical Specifications. D. DELETED E. DELETED F. DELETED G. Physical Protection The licens.ee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Pilgrim Nuclear Power Station Physical Security, Training and Qualification, and Safeguards Contingency Plan, Revision O" submitted by letter dated October 13, 2004, as supplemented by letter dated May 15, 2006. The licensee shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The licensee's CSP was approved by License Amendment No. 236, as supplemented by changes approved by Amendment Nos. 238, 241, 244, and 247. H. DELETED I. DELETED J. Conditions Related to the Sale and Transfer (1) DELETED (2) DELETED (3) DELETED (4) DELETED Amendment No. ###

(5) The Decommissioning Trust agreement(s) shall be in a form which is acceptable to the NRC and shall provide, in addition to any other clauses, that: a) Investments in the securities or other obligations of Holtec Pilgrim, Holtec Decommissioning International, their affiliates, subsidiaries or associates, or their successors or assigns shall be prohibited. In addition, except for investments tied to market indexes or other non-nuclear sector mutual funds, investments in any entity owning one or more nuclear power plants is prohibited. b) The Director, Office of Nuclear Reactor Regulation, shall be given 30 days prior written notice of any material amendment to the trust agreement(s). K. Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas: (a) Fire fighting response strategy with the following elements:

1. Pre-defined coordinated fire response strategy and guidance
2. Assessment of mutual aid fire fighting assets
3. Designated staging areas for equipment and materials
4. Command and control
5. Training of response personnel (b) Operations to mitigate fuel damage considering the following:
1. Protection and use of personnel assets
2. Communications
3. Minimizing fire spread
4. Procedures for implementing integrated fire response strategy
5. Identification of readily-available pre-staged equipment
6. Training on integrated fire response strategy
7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of:
1. Water spray scrubbing
2. Dose to onsite responders L. The licensee shall implement and maintain all Actions required by Attachment 2 to NRC Order EA-06-137, issued June 20, 2006, except the last action that requires incorporation of the strategies into the site security plan, contingency plan, emergency plan and/or guard training and qualification plan, as appropriate.

M. DELETED

4. DELETED Amendment No. ###
5. DELETED
6. DELETED
7. The information in the FSAR supplement, submitted pursuant to 10 CFR 54.21 (d), as supplemented by Commitments Nos. 3, 8, 9, 13, 15, 18, 19, 21, 22, 24, 25, 26, 27, 28, 30, 31, 33, 34, 35, 36, 37, 39, 40, 46, 51, and 52 of Appendix A of NUREG-1891, "Safety Evaluation Report Related to the License Renewal of Pilgrim Nuclear Power Station" dated June 2007, as supplemented, is henceforth part of the FSAR which will be updated in accordance with 10 CFR 50. 71 (e).

The licensee may make changes to the programs and activities described in the FSAR supplement and Commitments Nos. 3, 8, 9, 13, 15, 18, 19, 21, 22, 24, 25, 26, 27, 28, 30, 31, 33, 34, 35, 36, 37, 39, 40, 46, 51, and 52 of Appendix A of NUREG-1891, as supplemented, provided the licensee evaluates such changes pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

8. DELETED
9. DELETED
10. This license is effective as of the date of issuance and until the Commission notifies the licensee in writing that the license is terminated.

FOR THE NUCLEAR REGULATORY COMMISSION Original Signature on File Eric J. Leeds, Director Office of Nuclear Reactor Regulation

Attachment:

Appendix A - Permanently Defueled Technical Specifications (Radiological) Date of Issuance: TBD Amendment No. ###

APPENDIX A TO FACILITY LICENSE DPR-35 PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS AND BASES FOR PILGRIM NUCLEAR POWER STATION PLYMOUTH,MASSACHUSETTS Holtec Pilgrim, LLC and Holtec Decommissioning International Amendment No. ###

4.0 DESIGN FEATURES 4.1 Site Location Pilgrim Nuclear Power Station is located on the western shore of Cape Cod Bay in the Town of Plymouth, Plymouth County, Massachusetts and contains approximately 517 acres owned by Holtec Pilgrim as shown on FSAR Figures 2.2-1 and 2.2-2. The site boundary is posted and a perimeter security fence provides a distinct security boundary for the protected area of the station. The reactor (center line) is located approximately 1800 feet from the nearest property boundary. 4.2 Not Used 4.3 Spent Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum k-infinity of 1.32 for standard core geometry, calculated at the burnup of maximum bundle reactivity, and an average U-235 enrichment of 4.6 % averaged over the axial planar zone of highest average enrichment; and
b. Ke11 ~ 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in the applicable section of the FSAR.

4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 115 ft. 4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 3859 fuel assemblies. 4.3.4 Heavy Loads

a. Loads in excess of 2000 lb. shall be prohibited from travel over fuel assemblies in the spent fuel storage pool with the exception that heavy load handling over irradiated fuel in the Multi-Purpose Canister is permitted using a single-failure-proof handling system.
b. No fuel which has decayed for less than 200 days shall be stored in racks within an arc described by the height of the cask around the periphery of the leveling platform during cask handling operations in the spent fuel pool or when a cask is in the spent fuel pool.

Amendment No. ### 4.0-1}}

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