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:	Eric Thomas LeBoeuf, Lamb, Leiby & MacRae
To:	Case E Office of Nuclear Reactor Regulation
References
Download: ML17037C413 (28)

Text

U.S. NUCLEAR REGULATOR MMISSION DOCKET NUMBER N RC FoRM 195 r I2 78) 4d FILE NUMBER NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL FROM: DATE 0 OOCU NT XKHHK~ Mr. E. Case 'eBoeuf, Lamb,Leiby & MacRae Washington, D.C. 20036 DATE ECEI E E.B. Thomas, Jr.

OTO R IZED PROP INPUT FORM NUM R OF C PIES RECEIVED

@LETTER RIG COPY INAI UNC LASS IF I E D ZR I DEscRIPTIDN Ltr submitted on behalf of Niagnna Lic. No. DPR-63 Appl for Amend:

Mohawk Power Corp. trans the following: tech specs proposed change concerning chan es i 1P management & organization & trans Attchmt'

& B....... Notarized 7-21-77.-....

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LEBOEUF, LAMB, LEIBY 8L MAC RAE l757 N STREET, N.W.

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WAsHINGToN, D. C. 20036 TELEPHONE 202 457 7500 CASLE ADDRESS 3.EON A. ALLEN, JR. CAMERON F. M*cRAE 4 JOSEPH E. BACHKLDER,XIE CAMKRON F MACRAE>IIE 4 LESWIN>WASHINOTON> D C. J. LCSOEUF, JR. 1929-1975 ERNEST S. BALLARD>JR. GKRARD A.MAHER TCLCX> 440274 ADRIAN C. LKISY 1952 1976 G. S. PETER BERGEN 4 SHEILA H. MARSHALL G OFFRY D. C. BKST DAVID P. DICKS JAMES G. McKLROY JAMES P. McGRANKRY;JRF4

'ANDALL TAYLOR R. BRIGGS PHII.IP PALMER McOUIGAN 07 COUNSEL CHARLES N.BURGCR JAMES O'MALLKY,JR. 4 r THOMAS E.BURKE J. MICHAEL PARISH ARVIN K. UPTON ROGER D.FKLDMAN4 EUGENE R FIDELLFL JACOB FRIEDLANDER DONALD J. GREKNC JOHN A.RUDY PAUL G. RUSSELL HAROLD M. SKIDEL July 22, 1977 JAMES A. GREER 3E 4 CHARLES P. SIFTON 140 BROADWAY JOHN L.GROSE HALCYON G. SKINNER DOUGLAS W. HAWKS JOSEPH S. STRAUSS NKW YORK, N.Y. 10005 CARL D. HOBKLMAN SAMUEI M.SUGDEN O MICHAEL IOVKNKO 4>>> EUGENE B. THOMAS, JILi4 TELKPHONE 212 269 1100 JAMES F, JOHNSON> LEONARD M. TROSTEN L RONALD D. JONES HARRY H. VOIGT >4 CADLK ADDRESS LEX K. LARSONF4 H. RICHARD WACHTEL GRANT S, LEWIS GERARD P. WATSON LCSWIN, NCW YORK gk q~'X'COP% 8 TELEX: 423416 RESIDENT PARTNERS WASHINGTON OFFICE 4 ADMITTED TO THK DISTRICT OF COLUMBIA BAR 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

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION

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In the Matter of )

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NIAGARA MOHAWK POWER CORPORATION ) Docket No. 50-220 (Nine Mile Point Nuclear Station )

Unit No. 1) )

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 f5~~

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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 Executive Senior Vice President Vice President Manager Vice President Vice President

(}uality Assurance Engineering 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 Supervisor Supervisor Supezintcndent- TzaininS- Supe intendant Office-Ruclca Euclcar Results-Euclear Euclcaz Generation Generation Generation Superfntendcnt

)hfntcnance-

Ãuclear Assistant As s is tan't Supervisor Supervisor Supezvisor Supervisor Supervfsor Instru=cut & Instrument & Reactor Radfocbcnfcal &

Contzol- Rediochenical Rediaticn 6 Radfation Control-Ruclear Analysis Euc lear Protection Protcctfcn Supezvfsore*

Operations- Assistant Assistant

Ãuclear Assistant Assistant Supervisor Supervisor Supczviso>> Supcrvfsor Radiochenfcal Envfronncnta)

Instzunent & Reactor 6 Rsdiatfcn

~

I Control-Nuclear Analysis Protection Protection Statfon Shift+*

Supervfsor-Eucleaz Supervisor Assistant Electrfcal Supervisor lfafntcnancc- )hfntcnance- Technicians Technicians

Ãuclear Nuclear Technicians As Required As Required As Required

• 4-Shift Opcratfng Fozcnan

• 1-Pelicf Opezatoz B

• 4-Auxiliary Operator E-'8

• Opczator License Opezatoz P '1-Relic! <<e Senior Operator License 4-Auxiliary Operator C-8 Electricians Ymcharics 1-Rclicf Operator K As Required As Required The nornal station shift conplemat shall ccnsist of at least five pczsons 4-Auxiliazy Operator B includinS one licensed Senior Reactor Operator ard tvo licensed Reactor 1-Relfcf Op"zator B, Opc rators.

P

6. 3 Faci1 it Sta ff ual i fi 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: General Superintendent Nuclear Generation Member: Station Superintendent-Nuclear Generation Member: Superintendent Results-Nuclear Member: Supervisor Reactor Analysis Member: Superintendent Maintenance-Nuclear Member: Supervisor Instrument 8 Control-Nuclear Member: 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. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.

e. 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:

a ~ Recommend to the General Superintendent Nuclear Generation written approval or disapproval of items considered under 6.5. 1.6 (a) through (d) above.

b. 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.

C. 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.

Records 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 radiological safety g, mechanical and electrical engineering .

h. 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: Staff Engineer or Manager Member: General Superintendent. Nuclear Generation Member: Staff Engineer - Nuclear Member: Staff Engineer - Mechanical or Electrical Member: Staff Engineer - Environmental .

Member: 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 Re ortable Occurrence Action 6.6.1 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 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.

6.8 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