ML17264A103

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Issuance of Amendment No. 104, Administrative Changes to Technical Specifications Regarding Nuclear Safety Review Audit Committee
ML17264A103
Person / Time
Site: Pilgrim
Issue date: 08/25/1987
From: Wessman R
Office of Nuclear Reactor Regulation
To: Bird R
Boston Edison Co
References
TAC 60466
Download: ML17264A103 (1)


Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION Docket No. 50-2Q3 Roston Edison Company ATTN:

Mr. Ralph E. Bird WASHINGTON. D. C. 20555 August 25, 1987 S~ni-0r Vice President - Nuclear 800 Boy1ston Street Boston, Massachus!tts 02199

Dear Mr. Bird:

SUBL1ECT:

ISSUANCE OF AMENDMENT NO. 104 TO FACILITY OPERATING LICENSE NO, DPR-3.5 (TAC# ~0466)

The Commission has issued the enclosed Allll!ndment No. 104 to Facility Operating License No. OPR-35 for the Pilgrim Nuclear Power Station. This amendment consists of changes to the Technical Specifications in response to your application dated December 23, 1985 as supplemented by letters dated September 15, 1986 and February 19, 1987.

This amendment changes administrative practices and policies of the Nuclear Safety Review and Audit Cormiittee (NSRAC) allowing more efficient operation of the NSRAC within Technical Specification guidelines.

A copy of the related Safety Eva1uation is also enclosed. The Notice of Issuance will be included in the Commission's Bi-Weekly Federal Register Notice.

Enclosures:

1. Amendment No. 104 to License No. DPR-35.
2.

Safety Eva 1 uation Sincerely m T~f2..vl.,~

Richard H. Wessman, Senior ProJect Manager Project Directorate I-3 Division of Reactor Projects I/II cc w/enclosures:

Se.e next page RECEIVED AUG2 S~* i I

LICENSING.

Mr. Ralph G. Bird

~oston Edison Company cc:

Mr. K. P. Roberts, Nuclear Operations Pilgrim Nuclear Power Station Boston Edison Company RFD #lp Rocky Hill Road Plymouth 9 Massachusetts 02360 Resident Inspector's Office U. S. Nuclear Regulatory CormTission Post Office Box 867 Plymouth, Massachusetts 02360 Chairman, Board of Selectmen 11 linco1n Street Plymouth, Massachusetts 0?.360 Office of the Commissioner Massachusetts Oepart~nt of Environmental Duality Engineering One Winter Street Boston. Massachusetts 02108

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Dffi ce of the Attorney General 1 Ashburton Place 19th Floor Boston, Massachusetts 02108 Mr. Robert M. Hallisey, Director Radiation Control Program Massachusetts ~epartment of Public HP.a 1th 150 Tremont Street, 2nd Floor Boston, Massachusetts 02111 Regional Administrator, R~gion I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussiap P~nnsylvania 19406 Mr. James D. Keyes R@gulatory Affairs and Programs Group Lea_der Bost~n Edison Company 25 Braintree Hill Park Braintree, Massachusetts 02184 Pilgrim Nuc1ear Power Station Boston Edison Company ATTN:

Mr. Ralph G. Bird Senior Vice President - Nuclear 800 Boylston Street Boston, Massachus~tts 02199 Mr. Richard N. Swanson, Manager Nuclear Engineering Department Boston Edison Company 25 Braintree Hill Park Braintree, Massachusetts 02184 Ms. Elaine D. Robinson Nuclear lnformation Manager Pilgrim Nuclear Power Station RFD #1, Rocky Hill Road Plymouth, Massachusetts 02360

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UNITED ST ATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. I;:. 20555 BOSTON EDISON COMPANY DOCKET NO. 50-293 PILGRIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 104 License No. DPR-35

1.

Th~ Nuclear Regulatory Conmission (the Conmission) has found that:

A.

The application for amendment by Boston Edison Company (the licensee) datP.d December 23, 1985, as supplemented on September 15, 1986 and February 19, 1987 complies.with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangerin,g the health and safety of the public, and (it) that such activiti~s will be coriducted in compliance with the Corrmission's regulations; D.

Thia. issuance of this am~ndment will not be inimical to the common d~fense and security or to the health and safety of the public; and

. E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the ColTITlission's regulations and all applicable requirements have been satisfied.

2.

Accordingly 11 the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B. of Facility nperating. L fcensfl! No. OPR-35 is he?"eby amended to read as follows:

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Technical Specifications the Technfcal Specifications contained in Appendix A as revisP.d through Amendment No. M4 p are hereby incorporated fn the license. The licensee shal 1 operate the facility in accordance wfth the Technica 1 Specifications.

3. This 1fcense amendment is effective as of the date of its issuance.

Attachment:

Changes to the Technical Specifications FOR THE NUCLEAR REGULATORY COMMISSION "E\\Wµ___,

r Victor Nerses I Acting Director Project Directorate !-3 Division of Reactor Projects I/II Date of Issua~ce:

August 25, 1987

ATTACHMENT TO LICENSE AMENDMENT NO. 104 FACIL TIY OPERATING l ICENSE NO. DPR-35 DOCKET NO. 50-293 Replace the following pages of the Appendix 11A 11 Technical Spe'Cifications with the enclosed pages.

The revfsed page is identified by amendment number and contain vertical lines indicating the areas of change, The corresponding overleaf pages are provided to maintain document completeness.

Remove Pages 214

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B.

NUCLEAR SAFETY REVIE~ AND AUDIT COMMITTEE CNSRAC>

1.

FUNCTION The NSRAC shall function to provide lndependent review and audit of dasignated activities in the areas of:

l.

nuclear power plant operations;

2.

nuclear engineerln9;

3.

chemistry and radiochemistry; 4.

me ta l l ur 9 y ;

5.

f nstrumentation and control;

6.

radldloglcal safety;

7.

mechanical and electrical en~ineer1ng;

8.

quality assurance practices

9.

fire protection

2.

COMPOSITION The NSRAC Chairman and other members shall be appointed by the Senior Vice President - Nuclear.

The membership shall coJlectlvely possess a broad based level of experience and competence enabling the Committee to review and audlt those activities designated in 6.5.8.1 above and to recognize when it is necessary to obtain te.chnical advice and counsel.

The collective competence of the Committee will be maintained as changes to the membership are made.

The membership shall consist of a minimum of five persons of whom no more than a minority are members of the plant staff.

3.

ALTERNATES Alternate members shall be appointed ln writing by the Senior Vice President - Nuclear or the Chairman to serve on a temporary basls.

4.

CONSULTANTS Consultants shall be utilized as determined by the NSRAC Chairman to provide expert advice to the NSRAC.

5.

MEETING FREQUENCY The NSRAC shali meet at least once per six months.

6.

QUORUM A quorum of the NSRAC shall consist of the Chairman or his designated alternate and at least four NSRAC members including alternates.

The Vice Chairman is the designated alternate to the Chairman.

No more than a minority of the quorum shall have line responsibility for operation of the facility.

No more than ho a 1 ternates shall participate in a quorum at any one time.

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7.

REVIEW The NSRAC shall review:

a.

The written safety eva 1 uati ons for:

b..

c.
d.
e.

tl). changes in the fac*1llty as descrfbed in the F1na1 Safety Anal ys i s Report ;

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change,s ln the procedures descd bed 1 n Chapter 13.of the Final S.afety Analysis.Report; (3} te*st ~nq experiments not described in the Final Safety Analysfs Report to verify that such chariges. tests or experiments di*d not involve a change in the leelinic*a l Spedffcations or an unrev lewed safety question as defined in 10CFR50.5'9<a><2>.

Proposed changes to procedures, eaucioment or systems which invo'l ve an unreviewed' safety question as defined in Sec.t'ion 50.59., 10 CFR.

Proposed te:sts or experiments which involve an unreviewed safety que*d:Jon as d.efined'in Secti.on 50.59, 10 CFR.

Propo.sed changes in Technical Specifications.or operating Ucense.

Violations of aoplicable statute~. codei, Tegulations, orderj, Technical Spec:ifications, license requirements, or of internal procedures cir 1nstru~tions having nuclear safety signiffcance.

f.

Significant operating abnormaHties or deviations from normal and expected performance of p1arit equipment that ~ffect nuclear ~~f~ty.

g.

A 11 events wh 1 ch are required by l 0 CFR *SO. 73 to be reporte'd to the NRC in writing.

h.

Any o.ther matter involving safe operation of the nuclear plant whi.ch NSRAC deems appropr.iate for consideration or which is referred to NSRAC fot the onsitf operating organization or by other functional organizational* units w1th.ln. Boston Edison.

i.

Reports and meeting mtnute:s of* the Operations Revlew Committee.

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AUDITS Audits of fac.i Hty activities shall be performed under the cognizance of the NSRAC.

These audits shall encompass:

a. -The conformance of faci 1 ity operation to provisions contained within the Tec~nical Speclfitations and applicable license conditions at least once per year.
b.

The training and qualificatlons of the entire facility staff at least once ~er year.

Amen-dment No. l ~, J0, U. U. 10.d

d.
e.
f.
g.
h.

The results of all actions required by deftclencies occurring ln facl ltty equipme~t. structures~ systems or method of operation that affect nu:lsar safety at Jeast once per s1x months.

The per~ormance of all activities required by the Quality Assurance Program to meet the criterja of Appendix 11 6 11

, 10 CFR 50, at least once pef two years.

The Emergency Plan and implementing procedures at least once per two years.

The Station Security Plan and tmplementing procedures at least once per two years.

Any other area of facility operation considered appropriate by the NSRAC or the Senior Vice President - Nuclear.

The F1re Protectlcn Program and implementing procedures at least once per two years.

9.

AUiHORIT'f The NSRAC shall report to and advise tha Senior Vice Prasident -

Nuclear Dn those areas of responsibility specified ln Section 6.5.8.7 and 6.5.8.8.

10.

RECORDS Records of NSRAC activitles shall be prepared, approved and distributed as indicated below:

a.

Minutes of each NSRAC meeting shall be prepared, approved and forwarded to the Senior Vice President - Nuclear, NSRAC members, and others the Chatrman may designate.

b.

Reports of reviews encompassed by Section 6.5.B.7 e, f, g and h above, shall be prepared, approved and forwarded to the Senior V1ce President - Nuclear, with a copy to the Nuclear Operations Manager within 21 days following the completion of the review.

c.

Audtt reports encompassed by Section 6.5.B.8 above shall be forwarded to the Senior V,ce Pres1dent - Nuclear and to th~

management positions responsible for the areas audited within 30 days after completion of the audit.

6.6 REPORTABLE EVENT ACTION The fcl1owing actions shall be taken for each reportable event:

A.

The Commission shall be notified and or a report submitted pursuant to the requirements of either 10 CFR 50.72 or 10 CFR 50.73.

B.

Each Reportable Event Report submitted to the Commjssion sha11 be revlewea by tne ORC and submltted to the NSRAC Chairman and tbe Nuclear Operations Manag~r.

Amendment Na. ]0.

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UNITED STATES NUCLEAR REGULATORY COMMISSJON WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 104 1,0 INTR0DUCTTON TO FACILITY OPERATING LICENSE NO. OPR-35 BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 By letter dated December 23, 1985t supplemented by letters dated September 15, 1986 and February 19 9 1987 Boston Edison Company proposed and modified a change to the Technical Sp@cifications relative to the

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1icensee 1s Nuclear Safety Review Audit Committee (NSRAC).

2.0 EV/!.LU!l.TI(l~.:

The changes are administrative involving the Nuclear Safety Review and Audit Committee (NSRAC).

The changes bring the T@chnfca1 Specifications in line with current NSRAC administrative practices and policiesg thus allowing more efficient operat1on of NSRAC.

The changes a1so adds detail to clarify the composition of NSRAC. deletes redundant quorum reoui rernents and makes quorum requirements more specific than presently stated and details the specific types of safety evaluations ~hich NSRAC will review.

The changes ensure the effectiveness of NSRAC Meetings and defines the review responsibilities of the Committee.

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As described in their.1etter of February 19, 1987, BECo has made other changes in the Nuclear Operations Department at Pilgrim.

These changes were made partly in response to NRC concerns regarding manag~ment and orga nizatfona l weaknesses.

Theise changes include:

0 The Outage Management function has been transferred to Nuc1ear Operations and will report to the Nuclear Operations Manager.

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The Management Services Section of Nuclear Operations has been e Hmina ted.

The Fire Protection Group and the Nuclear Security Group have been re-assignerl from the Management Services Section to the Vice President Nuclear Operations.

The Compliance function from Management Services will now report to the Nuclear Engineering Departm~~t.

The Nuclear Training function from th~ Managements Services Section will report directly to the Vice President Nucl~ar Operations as a Section.

The Technical Section has been expanded to include a new Systems Group.

The Shift Technical Advisor function has been transferred from the Technical Section to the Operations Section.

These changes appear to be positivP steps and are expected to contribute to. the safe operation of Pilgrim.

ThP proposed ctranges revfse parts of Section 6 of the Administrative Technical Specific~~ions fo.r Pilgrim Nuclear Power Station. The changes are all adminis-tratfve in nature and clarify organizational and functional aspects of the NSRACo They do not physica11y affect plant safety related systems, and do not reduce any safety martjin.

3. 0 ENVIRONMENTAL CONSIDERATION.

This,amendment involves a c~ange to recordkeepfog, reporting o.r administrative procedures or requirements.

The staff has detenn1ned that the amendment involves '10 significant increase in the amounts. and no significant change in* the types, of any effluents that may be r~leased

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offsite, and that there 1s no significant ;ncreasl!I in individual or cumulative occupation*a1 radiation exposure.

The Co1t111ission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding. Accqrdingly, the amendment meets the e11gibf1ity criteria for categorical exclusion set forth in 10 CFR 51.22(c)(l0).

Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment ne~d be prepared in.connection wi~h the issuance of thi's amendment.

CONCLUSION Overal 1, we find that the changes proposed by the licensee do not detract from the effectiveness of th~ Technfca*l Specifications and that the resulting

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the Standard Review Plan.

Accordingly, we conclude that the proposed changps are acceptable:.

The staff has conc1uded, based on the consideratfons discussed. above, that (1) there is reasonable assurance that the hea1th and safety of the public will not be endangered by operation in the proposed mannerp and (2) suc.h activities will be conducted il"J coripliance with the Commissfon's regulations, and the issuance of the amendment will not be 1nimkal to the common deff!nse and security or to the health and safety of the public.

Dated:

August 25, l 987 Principal Contributor:

Owen Gormley