ML17037C413

Letter Enclosing Application for Amendment to Operating License and Proposed Changes to Technical Specifications Concerning Changes in Management and Organization

ML17037C413
Person / Time
Site:	Nine Mile Point
Issue date:	07/22/1977
From:	Thomas E B LeBoeuf, Lamb, Leiby & MacRae
To:	Case E G Office of Nuclear Reactor Regulation
References
Download: ML17037C413 (28)

Text

N RC FoRM 195 r I2 78)U.S.NUCLEAR REGULATOR MMISSION NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL DOCKET NUMBER 4d FILE NUMBER XKHHK~Mr.E.Case FROM: 'eBoeuf, Lamb,Leiby

&MacRae Washington, D.C.20036 E.B.Thomas, Jr.DATE 0 OOCU NT DATE ECEI E@LETTER RIG INAI COPY OTO R IZED UNC LASS IF I E D PROP INPUT FORM NUM R OF C PIES RECEIVED ZR I DEscRIPTIDN Ltr submitted on behalf of Niagnna Mohawk Power Corp.trans the following:

1P Lic.No.DPR-63 Appl for Amend: tech specs proposed change concerning chan management

&organization

&trans Attchmt'&B.......Notarized 7-21-77.-....

(3 Orig&40 CC recI d)12P es i g0 gQT REMOVE Nine Mile Pt.Unit 1 DHL"7-25-77 FOR ACTION/INFORMATION ACKNOWLEDGEQ ENVIRHNMENTAL T MANAGER: EN ING ASSXSTANT:

ASSIGNED AD: V MOORE LTR BRANCH CHIEF: PROJECT MANAGER: LICENSING ASSISTANT:

Bo HARLESS INTERNAL D ISTRI BUTION TFMS SAFETY HEINEMAN OEDE PLANT SYSTEMS TEDESCO BENAROYA SITE SAFETY&ENVIRON ANALYSIS DENTON&MULLER ENGINEERING IPPOLITO OPERATING REACTORS ENVIRO TECH ERNST BLOO B ER Js 1~GAMMILL 2 CHECK AT I TZMAN ERG EXTERNAL DISTRIBUTION SITE ANALYSIS VOLI MR BUNCH J%COLLINS cKMI'R CONTROL NUMBER TIC RE TV J HANCHETT 16 CYS ACRS SENT CAT NRC FORM 195 I2.76)GO NSIC 772060053 0'1 LEBOEUF, LAMB, LEIBY 8L MAC RAE l757 N STREET, N.W.WAsHINGToN, D.C.20036~98>>IOFI>,l+/I Cj>>3.EON A.ALLEN, JR.JOSEPH E.BACHKLDER, XIE ERNEST S.BALLARD>JR.G.S.PETER BERGEN 4 G OFFRY D.C.BKST DAVID P.DICKS TAYLOR R.BRIGGS CHARLES N.BURGCR THOMAS E.BURKE ROGER D.FKLDMAN4 EUGENE R FIDELLFL JACOB FRIEDLANDER DONALD J.GREKNC JAMES A.GREER 3E 4 JOHN L.GROSE DOUGLAS W.HAWKS CARL D.HOBKLMAN MICHAEL IOVKNKO JAMES F, JOHNSON>4>>>RONALD D.JONES LEX K.LARSONF4 GRANT S, LEWIS CAMERON F.M*cRAE 4 CAMKRON F MACRAE>IIE 4 GKRARD A.MAHER SHEILA H.MARSHALL JAMES G.McKLROY JAMES P.McGRANKRY; JRF4 PHII.IP PALMER McOUIGAN JAMES O'MALLKY, JR.4 J.MICHAEL PARISH JOHN A.RUDY PAUL G.RUSSELL HAROLD M.SKIDEL CHARLES P.SIFTON HALCYON G.SKINNER JOSEPH S.STRAUSS SAMUEI M.SUGDEN EUGENE B.THOMAS, JILi4 LEONARD M.TROSTEN L HARRY H.VOIGT>4 H.RICHARD WACHTEL GERARD P.WATSON RESIDENT PARTNERS WASHINGTON OFFICE 4 ADMITTED TO THK DISTRICT OF COLUMBIA BAR TELEPHONE 202 457 7500 CASLE ADDRESS LESWIN>WASHINOTON>

D C.TCLCX>440274 r July 22, 1977 gk q~'X'COP%'ANDALL J.LCSOEUF, JR.1929-1975 ADRIAN C.LKISY 1952 1976 07 COUNSEL ARVIN K.UPTON 140 BROADWAY NKW YORK, N.Y.10005 O TELKPHONE 212 269 1100 CADLK ADDRESS LCSWIN, NCW YORK 8 TELEX: 423416 Mr.Edson G.Case Acting Director Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555, Re: Niagara Mohawk Power Corporation Nine Mile point.Nuclear Station', Unit No.1'Do'cket-No'.'50-220

Dear Mr.Case:

As counsel for Niagara Mohawk, I enclose the following:

(1)Three (3)originals and nineteen (19)copies of an application for amendment to operating license;and (2)Forty (40)copies each of two (2)documents en-titled Attachments A and B which set forth the requested change in the Technical Specifications along with its technical basis.Very truly yours, LeBOEUF, LAMB, LEIBY 6 MacRAE By Euge B.Thomas, Jr.Enclosure 7720b0053 0 l',*g l I/I I~h (1+,'l I C S Ih I I I I*I'ph I (, h~'I h,l(,~I h v ,P CP I II 3 I'k ('2 I(I" I I hl I I I(I'1(P',.)~Pj(I jl Q UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of)))NIAGARA MOHAWK POWER CORPORATION

)(Nine Mile Point Nuclear Station)Unit No.1))~Re a org'Jgjq PQ<Docket No.50-220 APPLICATION FOR AMENDMENT TO OPERATING LICENSE Pursuant to Section 50.90 of the regulations of the Nuclear Regulatory Commission, Niagara Mohawk Power Cor-poration, holder of Facility Operating License No.DPR-63, hereby-reques'ts that Sections 6.5.1.2, 6.5.1.6, 6.5.1.7, 6.5.1.8, 6.5.2.2, 6.5.2.8, 6.5.2.9, 6.5.2.10, 6.6.1, 6.7.1 and Figures 6.2-1 and 6.2-2 of the Technical Specificati'ons and Bases set forth in Appendix A to that License be'amended.The proposed changes have been concurred-with by.the'Si,te Operations Review Committee and the Safety Rev'iew and Audit Board.-The'proposed Technical Specificati.on changes are set forth in Attachmen't A to this application.

Supporting Information, whi;ch'demonstrates that the"proposed changes do not involve'a significant hazards consideiation, is set forth in Attachment B.The proposed changes would not authorize'any change'in the types or any increase in the amounts of effluents or any change'in the authorized power level of the facility.

~~~~~~~~~~

'WHEREFORE, Applicant respectfully requests that Appendix A to Facility Operating License No.DPR-63 be ,amended in the form attached hereto as Attachment A.NIAGARA.NOHAWK POWER CORPORATION Gerald K.Rhode Vice President-Engineering Subscribed and sworn to before me this gJ~day of July, 1977.NOTARY PUBLI~PHYLLIS 0., VOYTKO Notrrry Putrlic fn the t;tote of flew York Qrretrf'crf ht onon.Co.tfo.34-5e85535

~Mv Cnrnrnse~p!n frrptree Mrrrch 30.f5~

0 ATTACHMENT A Niagara Mohawk Power Corporation License No.DPR-63 Docket No.50-220 Pro osed Chan es to Technical S ecifications Attached are revised Pages 246, 247, 249, 250, 251, 252, 255 and 256.

Figure 6.2-l Nine Mile Point Nuclear Station Management Organization Chart President Senior Vice President Executive Vice President Manager (}uality Assurance Vice President Engineering Vice President Electric Production General Superintendent Nuclear Generation Station Superintendent Nuclear Generation 246

FIGURE 6!2-2 EIRE MILE POINT hUCLAR SITE OPERATIC ORGARIZATIOS Cerebral Superintendcnt-Ruclcar Generation Assistants to the Supcrintcndcnt As Rcquircd Station Supezintcndent-Ruclca Generation Supervisor TzaininS-Euclcar Generation Supe intendant Results-Euclear Supervisor Office-Euclcaz Generation Superfntendcnt)hfntcnance-

Ãuclear Assistant Supervisor Instru=cut

&Contzol-Euc lear As s is tan't Supezvisor Rediochenical 6 Radfation Protection Supervisor Instrument

&Control-Ruclear Supervfsor Reactor Analysis Supervisor Radfocbcnfcal

&Rediaticn Protcctfcn Supezvfsore*

Operations-

Ãuclear Assistant Supervisor Instzunent

&Control-Nuclear Assistant Supervisor Reactor Analysis Assistant Supczviso>>

Radiochenfcal 6 Rsdiatfcn Protection Assistant Supcrvfsor I~Envfronncnta)

Protection Statfon Shift+*Supervfsor-Eucleaz*4-Shift Opcratfng Fozcnan*1-Pelicf Opezatoz B*4-Auxiliary Operator E-'8'1-Relic!Opezatoz P 4-Auxiliary Operator C-8 1-Rclicf Operator K 4-Auxiliazy Operator B 1-Relfcf Op"zator B, Supervisor Electrfcal lfafntcnancc-

Ãuclear Electricians As Required Assistant Supervisor)hfntcnance-Nuclear Ymcharics As Required Technicians As Required Technicians As Required Technicians As Required*Opczator License<<e Senior Operator License The nornal station shift conplemat shall ccnsist of at least five pczsons includinS one licensed Senior Reactor Operator ard tvo licensed Reactor Opc rators.

P

6.3 Faci1

i t Sta f f ual i f i cati ons 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions.

6.4~Trainin 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Supervisor and shall meet or exceed the requirements and recom-mendations of Section 5.5 of ANSI N18.1-1971 and Appendix"A" of 10 CFR Part 55.6.5 Review and Audit 6.5.1 Site 0 erations Review Committee SORC Function 6.5.1.1 The Site Operations Review Committee shall function to advise the General Superintendent Nuclear Generation on all matters related to nuclear safety.Com osition~-6.5.1.2 The Site Operations Review Committee shall be composed of the: Chairman: Member: Member: Member: Member: Member: Member: General Superintendent Nuclear Generation Station Superintendent-Nuclear Generation Superintendent Results-Nuclear Supervisor Reactor Analysis Superintendent Maintenance-Nuclear Supervisor Instrument 8 Control-Nuclear Supervisor Radiochemical 5 Radiation Protection 249 s

Alternates 6.5.1.3 Alternate members shall be appointed in writing by the SORC Chairman to serve on a temporary basis;however, no more than two alternates shall participate in SORC activities at any one time.Heetin Fre uenc 6.5.1.4 The SORC shall meet at least once per calendar month and as convened by the SORC Chairman.uorum 6.5.1.5 A quorum of the SORC shall consist of the Chairman and four members including alternates.

Res onsibi1 i ties 6.5.1.6 The Site Operations Review Committee shall be responsible for: a.Review of 1)all procedures required.by Specification 6.8 and changes thereto, 2)any other proposed procedures or changes thereto as determined by the General Superintendent Nuclear Generation to affect nuclear safety.b.Review of all proposed tests and experiments that affect nuclear safety.c.Review of all proposed changes to the Technical Specifications.

d.e.Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.Investigation of all violations of the Technical Specifications and shall prepare and forward a report covering evaluation and recommendations to prevent recurrence to the Vice President-Electric Production and to the Chairman of the Safety Review and Audit Board.250

~Rebill i r'd)f.Review of facility operations to detect potential safety hazards.g.Performance of special reviews and investigations and reports thereon as requested by the Chairman of the Safety Review and Audit Board.h.Review of the Plant Security Plan and implementing procedures and shall submit recommended changes to the Chairman of the Safety Review and Audit Board.i.Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Chairman of the Safety Review and Audit.Board.~Author it 6.5.1.7 The Site Operations Review Committee shall: Records a~b.C.Recommend to the General Superintendent Nuclear Generation written approval or disapproval of items considered under 6.5.1.6 (a)through (d)above.Render determinations in writing with regard to whether or not each item considered under 6.5.1.6 (a)through (e)above constitutes an unreviewed safety question.Provide immediate written notification to the Vice President-Electric Production and the Safety Review and Audit Board of disagreement between the SORC and the General Superintendent Nuclear Generation; however, the General Superintendent Nuclear Generation shall have responsibility for resolution.of such disagreements pursuant to 6.1.1 above.6.5.1.8 The Site Operations Review Committee shall maintain written minutes of each meeting and copies shall be provided to the Vice President-Electric Production and Chairman of the Safety Review and Audit Board.251

6.5.2 Safet

Review and Audit Board SRAB Function 6.5.2.1 The Safety Review and Audit Board shall function to provide independent review and audit of designated activities in the areas of: a.nuclear power plant operations b.nuclear engineering c.chemistry and radiochemistry d.metallurgy e.instrumentation.and control g, h.radiological safety mechanical and electrical engineering

.quality assurance practices (other appropriate fields associated with the unique characteristics of the nuclear.power plant)~~Citi 6.5.2.2 The Safety Review and Audit Board shall be composed of the: Chairman: Member: Member: Member: Member: Member: Staff Engineer or Manager General Superintendent.

Nuclear Generation Staff Engineer-Nuclear Staff Engineer-Mechanical or Electrical Staff Engineer-Environmental

.Consultant (See 6.5.2.4)252 I'

Audits (coot'd)d.The performance of all activities required by the guality Assurance Program to meet the criteria of Appendix"B", 10 CFR 50, at least once per two years.e.The Facility Emergency Plan and implementing procedures at least once per two years.f.The Facility Security Plan and implementing procedures at least once per two years.g.Any other area of facility operation considered appropriate by the SRAB, the Vice President-Electric Production or the Vice President-Engineering.

~Authori t 6.5.2.9 The SRAB shall report to and advis'e the Vice President-Electric Production and Vice President-Engineering on those areas of responsibility specified in Section 6.5.2.7 and 6.5.2.8.Records 6.5.2.10 Records of SRAB activities shall be prepared, approved and distributed as indicated below: a.Minutes of each SRAB meeting shall be prepared, approved and forwarded to the Vice President-Electric Production and Vice President-Engineering within 30 days following each meeting.b.Reports of reviews encompassed by Section 6.5.2.7 e,f,g and h above, shall be prepared, approved and forwarded to the Vice President-Electric Production and Vice President-Engineering within 14 days following completion of the review.c.Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Vice President-Electric Production and Vice President-Engineering and to the management positions responsible for the areas audited within 90 days after completion of the audit.255

6.6 6.6.1 Re ortable Occurrence Action The following actions shall be taken in the event of a REPORTABLE OCCURRENCE:

a 0 The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.b.Each Reportable Occurrence Report submitted to the Commission shall be reviewed by the SORC and submitted to the SRAB and the Vice President-Electric Production.

6.7 Safet

Limit Violation 6.7.1 6.8 The following actions shall be taken in the event a Safety Limit is violated: a.The provisions of 10 CFR 50.36(c)(1)(i

)shall be complied with immediately.

b.The Safety.Limit violation shall be reported to the Commission, the Vice President-Electric Production and to the SRAB immediately.

c.A Safety Limit Violation Report shall be prepared.The report shall be reviewed by the SORC.This report shall describe (1)applicable circumstances preceding the violation, (2)effects of the violation upon facility components, systems or structures, and (3)corrective action taken to prevent recurrence.

d.The Safety Limit Violation Report shall be submitted to the Commission, the SRAB and the Vice President-Electric Production within 10 days of the violation.

Procedures

6.8.1 Written

procedures and administrative policies shall be established, implemented and maintained that meet or exceed the requirements and recommendations of Sections 5.1 and 5.3 of ANSI N18.7-1972 and Appendix"A" of USAEC Regulatory Guide 1.33 except as provided in 6.8.2 and 6.8.3 below.256 P

ATTACHMENT B Niagara Mohawk Power Corporation License No.DPR-63 Docket No.50-220 Su ortin Information The proposed changes are being made to: 1)eliminate the James A.FitzPatrick Nuclear Power Plant from the Nine Mile.Point Nuclear Site Organization (Figure 6.22)2)to eliminate representation of the Power Authority of the State of New York from the Site Operations Review Committee and Safety Review and Audit Board and 3)to reflect changes in the Niagara Mohawk onsite and offsite organizations.

These proposed changes reflect the changes in operating responsibility for the James A.FitzPatrick Nuclear Power Plant.These changes also reflect current Niagara Mohawk onsite and offsite organization for facility management.

It is expected that the new organization will improve facility management and provide for more effective reporting.

The Site Operations Review Committee and the Safety Review and Audit Board will retain adequate membership to provide the expertise required by ANSI N18.7-1972.

A