ML20054K993

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Amends 85,50 & 78 to Licenses DPR-21,DPR-61 & DPR-65, Respectively,Reflecting Recent Organizational Changes & Increasing Millstone in-plant Fire Brigade from Three to Five Members
ML20054K993
Person / Time
Site: Millstone, Haddam Neck, 05000000
Issue date: 06/25/1982
From: Crutchfield D
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20054K992 List:
References
NUDOCS 8207070040
Download: ML20054K993 (38)
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'o, UNITED STNTES NUCLEAR REGULATORY COMMISSION _.^

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  • ' '" ' E WASmhGTON. D. C. 20555 o S, hf a, t,; % - y THE CONNECTICUT YANKEE ATOMIC POWER COMPANY DOCKET N0. 50-213 HADDAM NECK PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 50 License No. DPR-61 1.

The Nuclear Regulatory Commission (the Comission) has found that:

A.

The application for amendment by the Connecticut Yankee Atomic Power Company (the licensee) dated February 24, 1982, 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 r egulations of -

the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense 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 Comission's regulations and all applicable requirements have been satisfied.

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8207070040 820625 PDR ADOCK 05000213 P

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Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-61 is hereby amended to read as follows:

(2)

Techical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 50 are hereby incor-porated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 9

45 AW dg(,

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s ffvDennis M. Crutchfield, Chief Operating Reactors Branch #5 Disision of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: June 25, 1982 i

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o ATTACHMENT TO LICENSE AMENDMENT NO. 50 FACILITY OPERATING LICENSE NO. DPR-61 DOCKET NO. 50-213 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Delete Page Insert Page 6-2 6-2 6-6 6-6 6-7 6-7 6-12 6-12 6-13 6-13 1

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(;0NNECTICUT YANKEE ATOMIC POWER COMPANY OFFSITE ORCANIZATION l

CYAPC PRESIDENT NUSCO PRESIDENT AND CllIEF OPERATING OFFICER CYAPC VICE PRESIDENT NUSCO SENIOR VICE PRESIDENT

' NUCLEAR ENGINEERING AND l

OPERATIONS

  • NUCLEAR REVIEW ROARD i

w NUSCO VICE PRESIDENT NUCLEAR OPERATIONS

---OFFSITE-

- - - = = = - - - - - - -

F NUCLEAR OPERATIONS CONNECTICUT YANKEE STATION STAFF SUPERINTENDENT - ONSITE

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  • Provides Operating and 5

Technical Support by l

i Contractural Arrangement 2

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is Figure 6.2-l' i

ADMINISTRATIVE CONTROLS ALTE RNATES 6.5.1.3 Alternate members shall be appointed in writing by the PORC Chairman to serve on a temporary basis; however, no more than two alternates shall participate in PORC activities at any one time.

MIETING FRECUENCY 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairman.

QUORUM 1

j 6.5.1.5 A quorum of the PORC shall consist of the Chairman and four members including alternates.

RESPONSIBILITIES 6.5.1.6 The PORC shall be responsible for:

i a.

Review of 1) all procedures required by Specification 6.8 and changes thereto, 2) any other proposed procedures or changes thereto as determir.ed by the Station Super-

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intendent to affect nuclear safety.

b.

Review of all proposed tests and experiments that affect nuclear safety, i

c.

Review of all proposed changes to the Technical Specifications,

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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 Nuclear Operations and to the Chairman of the Nuclear Review Board.

f.

Review of facility operations to detect potential safety hazards.

6-6 Amendment No. 5, 26, 50

c..

ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued) g.

Performance of special reviews and investigations and reports thereon as requested by the Chairman of the Nuclear Review Board.

h.

Review of the Plant Security Plan and implementing procedures and shall submit recommended changes to the Chairman of the Nuclear Review Board.

f.

Review of the Emergency Plan and implementing procedures and shall submit recommended. changes to the Chairman of the Nuclear Review Board.

j.

Render determinations in wrir.ing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.

AUTHORITY 6.5.1.7 The PORC shall:

a.

Report to and be advisory to the Station Superintendent on those areas of responsibility specified in Section 6.5.1.6 and 6.5.1.8.

b.

See 6.5.1.6.j above.

Provide timely written notification, meeting minutes c.

may be used for this purpose, to the Vice President Nuclear Operations and the Chairman of the Nuclear Review Board of disagreement between the PORC and the Station Superintendent however, the Station Superintendent shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

RECORDS

6. 5.1. 8 The PORC shall maintain written minutes of each meeting and copies shall be provided to the Vice President Nuclear Operations and Chairman of the Nuclear Review Board.

6-7 Amendment No. 36,50

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a ADMINISTRATIVE CONTROLS RECORDS 6.5.2.10 Records of NRS activities shall be prepared, approved and distributed as indicated below:

Minutes of each NR3 meeting shall be prepared, approved a.

and forwarded to the Senior Vice President-Nuclear Engineering and Operations within 14 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 Senior Vice President-Nuclear Engineering and Operations with 14 days following completion of the review. 'ieeting minutes may be used for this purpose.

Audit reports encompassed by Section 6.5.2.8 above, c.

shall be forwarded to the Senior Vice President-Nuclear Engineering and Operations and to the management positions responsible for the areas audited within 30 days after completion of the audit. Meeting minutes may be used for this purpose.

QUALIFICATIONS 6.5.2.11 Minimum qualifications of NRB me=bers are as follows:

Academic degree in an engineering or physical science a.

field or equivalent as per Section 6.5.2.11.c.

b.

Minimum of five years technical experience, of which a minimum of three years is in one or more of the areas specified in Section 6.5.2.1.

Technical experience in the areas specified in Section c.

6.5.2.1 beyond the three year minimum may be substituted on a one for one basis towards the academic degree requirement.

(Four years of technical experience being equivalent to a four year academic degree).

total a d.

Total a:ademic and technical, experience must minimum of nine years.

6-12 Amendment No. 77, 36, 50

9 ADMINISTRATIVE CONTROLS REPORTABLE OCCURRESCE ACTION 6.6 The following actions shall be taken for all events which 6.6.1 are required by regulations of Technical Specifications to be reported to the NRC in writing within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, submitted The Commission shall be notified and/or a report to the requirements of Specification 6.9.

a.

pursuant submitted to the Each Reportable Occurrence Report b.

Commission shall be reviewed by the PORC and submitted to the NR3 and the Vice President Nuclear Operations.

6.7 SAFETY LIMIT VIOLATION a Safety The following actions shall be taken in the event 6.7.1 I

Limit is violated.

a.

The unit shall be placed in at least HOT STANDBY within one hour.

The NRC Operations Center shall be notified by telephone as soon b.

The Vice President as possible and in all cases within one hour.

Nuclear Operations and the NRB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

l shall be prepared. The I

A Safety Limit Violation Report c.

shall be reviewed by the PORC. This report report shall describe (1) applicable circumstances preceding the violation, (2) ef fects of the violction upon i

facility components, systems or structures, and (3) recurrence, corrective action taken to prevent The Safety Limit Violation Report shall be submitted d.

to the Commission, the NR3 and the Vice President-Nuclear Operations within 14 days of the violation.

6.8 PROCEN?RES L'rit*.en procedures and administrative policies shall be established, implemented and maintained that meet or exceed 6.8.1 the requirements and recccmendations of Section 5.1 and 5.3 of ANSI N18.7-1976 and Appendix "A" of USAEC Regulatory as provided in 6.8.2 and 6.8.3 below.

Guide 1.33 except Procedures shall be established and maintained for implementation of the Facility Fire Protection Program.

Each procedure and administrative policy of 6.8.1 above, reviewed by the PORC and approved 6.8.2 and changes thereto, shall te by the Station Superintenuant prior to implementation and periodically as set forth in each document.

6-13 Amendment No. 24, 36, 50 1

[;.nco.'o, UNITED STATES

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c., ',g NUCLEAR REGULATORY COMMISSION

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E WASHINGTON. D. C. 20555

%,4.m...f.f THE CONNECTICUT LIGHT AND POWER COMPANY, THE HARTFORD ELECTRIC LIGHT COMPANY, WESTERN MASSACHUSETTS ELECTRIC r^"DANY, AND NORTHEAST NUCLEAR ENERGY COMPANY DOCKET NO. 50-245 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 1 i

AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 85 License No. DPR-21 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by the Connecticut Light and Power Company, The Hartford Electric Light Company, Western Massachusetts Electric Company, and Northeast Nuclear Energy Company (the licensees) dated February 24, 1982, 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; 8.

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 endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; t

D.

The issuance of this amendment will not be inimical to the common l

defense 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 Commission's regulations and all applicable requirements have been satisfied.

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DESIGIIATED ORIGIITAL Co 1;1fied Bf

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. 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 3.B of Provisional Operating License No. DPR-21 is hereby amended to read as follows:

3.8 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 85, are hereby incorporated in the license. Northeast Nuclear Energy Company shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 1

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./'144 v u

/9 Dennis M. Crutchfield, Chief Le Operating Reactors Branch #5 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

June 25, 1982

ATTACHMENT TO LICENSE AMENDMENT NO. 85 FACILITY OPERATING LICENSE NO. DPR-21 DOCKET NO. 50-245 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Delete Page Insert Page 6-1 6-1 6-2 6-2 6-4 6-4 6-5 6-5 6-6 6-6 6-7 6-7 6-9 6-9 6-11 6-11 6-15 6-15 6-16 6-16 6-18 6-18 l

Millstone Unit 1 6.0 A.**'I k! S* RAT IVE C0h~20L5 6.1 RESPON5!!!LITY 6.1.1 The Station Superintendent shall be responsible for evere11 operation cf the W.iilst:ne Station Site wnile the Unit Superintendent shall be respon-sible for operati:n of the unit. The Station Superintendent and Unit Superin-tendent snt11 eacn delegate in writing the succession to these responsibilities during their absence.

6.2 OR1'N!ItTION OT SITE 6.2.1 The offsite organi:stien for facility management and technical su;;;rt shall de as she-m in Figure 6.2-1.

FAC!LITY FTAFF 6.2.2 The Fa:iliky o?;ani:ation shall be as shown en Figure 6.2-2 and:

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La:h en duty shift shall be comp: sed of at least the minimem a.

shif t cre. :sm;:sition sho-m in Table 6.2-1.

b.

At least ene licensed Operater shall be in the c:ntrol room when fuel is in the rea:ter.

At least two licensed Operaters shall be present in the~

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cent ci room during reacter start-up, scheduled react:r shutdow.

and d. ring re::very from reacter trips.

An indivicual cualified in radiation pr:tection procedures shall c.

be en site when fuel is in the reactor.p All CCEE ALTERATIONE af ter the initial fuel leading shall be e.

directly su:ervise: by either a licensed Senice React:r Cperate-er Senior React:r 0;erator list'ed t: Fuel Handling wh: has no cther c:n:urren* resp:nsibilities during this cperation.

f.

A51:e Fire Bricade of 5 nenbers shall be maintained onsite at all l

ti,45.8 The Fire Eri;3de shall not in:1ude the minimum shift e re:essary f:r safe shutd:st. Of the 'Jat t (2 nee.bers) or any pers:nnel required f:r other essential functices during a fire ecer;en:y.

6.3 FaCIL 7Y STAFF QUALIFICATIONS Ea:n cember of the facility staff shall meet or eiceed the minimum 6.3.1 for comparable positions, except for (1)

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cualifications of AN51 N16.1-1971 the Health Pn/ sics Superviser whf shall meet or exceed the qualifications of Ee;atat:ry Guide 1.5, Revision 1, and (2) the Shif t Te:hnical Adviser who shall ra,e a Eacheier's Degree er equivalent in a scientific or engineering

' dit:ipline with spe:ific training in plant design, and response and analysis

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cf :te plant f r transients and accidents.

  1. See Note o n Page 6-4.

7/,32,//,44[,85

' 6-1 A'e-areat No.

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TASLE 6.2-1 MINIMUM SHIFT CREV COMPOSITION' APPLICABLE MODES LICENSE CATEGORY

1. 2 & 3" 4 & 58 SOL 1

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OL 2-1 Non-Licensed 2

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None Required Shift Technical Advisor

  • Does not include the licensed Senior Reactor or Senior Reactor Operator

, Limited to Fuel Handling individual supervision CORE ALTERATIONS after the initial fuel loading.

  1. The above shif t crew composition and the qualified health physics technician and/or fire brigade members of Section 6.2.2 may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence provided expeditious actions are taken to fill the required positions.
    • Reactor Mode Switch Position is in RUN (any average coolant temperature)

STARTUP/ HOT STANDBY (any average coolant temperature), and HOT SHUTDOWN (average coolant temperature greater than 212 F), respectively.

    1. Reactor Mode Switch Position is in SHUTDOWN (average coolant temperature less than 212 F) and REFUELING (average coolant temperature less than 212 F),

respectively.

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i Amend.eent No.

85 6-4

, NJ".!h!57RATIVE CONTRT.5 6.4 T R.A ! N I N *,

A retraining and replacemnt training program for the facility staf f 6.4.1 shall be maintained under the direction of the Station Suce"intendent and it.a'.I meet or exceed the re:;sirements and reccmevations of Section 5.5 of AN51 N18.1-1971 and Appendia "A" of 10 CFR Part 55.

A trainin; prograe for the Fire Brigade shall be maintained under 6.4.2 the direction of the Training Saoe visor and shall meet or exceed the eer.t rements of Section 27 of the NFPA Code - 1975. esteet that Fire Brigadetrainingsessionsshallbeheldatleastquarterly.

E.5 REV!EV AN A'J !T PLAN' 0:E u~!ONS REviEV C P "!TTEE (P020) i.F.1 rL'N *T I ON The POR* shal1 f unction to advise the Unit Superintender.t on

'f.5.1.1 all F.atters relatet to nWelear safety.

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6. E.1. 2 The FCE" shall be co.-' posed of the; Unit Superintendent Chairm n:

Vice Chairm n Operations Supervisor

& Mer.oe-:

Maintenance Supervisor Me-ber:

Instrument and Control Superviser Me-ber:

Reactor Engineer Meecer:

Eneineerino Supervisor or Startuo Sunervis.or' Meezer:

Member:

Station Services Superintendent or General l

Services Supervisor or Quality Services Super-l visor or Radiological Services Supervisor Staff Engineer **

Lerber:

ALTERN'TES Cha i mar.

Alternate merte s shall be appointed in writing by the POR to serve on a temporary basis; however. no mere than two alternates shall

6. f.1. 3 participate in POR: activities at any one time.

' amen position is staffed.

The Staff Engineer me-ber of the PORC shall have an academic degree in engineering or physical science field; and in addition, shall have a minirv. of five years technical experience, of which a minimsm of three years shall be in the nuclear power plant industry.

4-5 Arendunt No. H. 33. 31. F, ff, f, 85

k ADMINISTRATIVE CONTROLS MEETING FREQUENCY The PORC shall meet at least once per calendar month and as convened 6.5.1.4 by the'PORC Chairman.

0000UM 6.5.1.5 A quorum of the PORC shall consist of the Chairman or Vice Chairman or Station Sacerintendent and four members includino alternates.

PESDONSIBILITIES 6.5.1.6 The POR: shall be responsible for:

Review of 1) all procedures, except common site procedures, required a.

by Spe:ification 6.8 and changes thereto, 2) any other proposed pro:edures or changes thereto as determined by the Unit Superintendent to affect nu: lear safety.

of all proposed tests and experiments that affect nuclear b.

Review safety.

Review of all proposed changes to Se:tions 1.0 - 5.0 of these

  • c.

Technical Specifications.

Review of all proposed changes or modifications to plant systems d.

or eqaipnent that affect nuclear safety, Investigation of all violations of the Technical Spe:ifications and preparation and forwarding of a report covering evaluation e.

and recom endations to prevent recurrence to the Vice Pres-Nuclear Operations and to the Chairman of the Nuclear ident Review Board.

Review of events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Consission, f.

Review of facility operations to dete:t potential safety hazards.

g.

Performance of special reviews and investigations and reports thereon as requested by the Chairman of the Nu: lear Review Board.

h.

Render determinations in writing with regard to whether or not each 1.

item considered under 6.5.1.6(a) through (e) above consitutes an unreviewed safety question.

S,

, 85 6-6

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Amendment N. 7J, D,

AO"!NISTPAilVE CONTROLS

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6. 5.1. 7 The PORC shall:

a.

P.ecommend to the Unit Superintendent written ap;*3 sal ce disapproval of items corsidered under 6.5.1.6(a) throsgt (d) abo <e.

b.

Pr:vice im eciate written notificattor. to the Statier. Suoerintencent, Vice President Nuclear Operations and the Chairman of the :luclear Review Board of disagreement between the PORC and the Unit Superin-tendent; however, the Unit Superintendent shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

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Nu: lea 0:erations and Chairman cf the Nuclear Peview Board.

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  • ee 50:0 s*al' fun:tton te advise tne Stetton Suterintendert on all e.a t t e r ; reta.e: te nsclear safety of the entire Millstere Sta*for Site.

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' ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued)

Render determinations in writing or meeting minutes with regard to h.

whether er not each item considered under 6.5.2.6(a) through (g) above constitutes an unreviewed safety question.

AUTHORITY 6.5.2.7 The 50RC shall:

Recommend to the Station Superintendent written accroval or disapproval a.

. in meeting minutes of items considered under 6.5.2.6(a) through (g) a bov e, Provide immediate written notification or meeting minutes to the l

b.

Vice President Nuclear Operations and the Chairman of the Site Nuclear Review Board of disagreement between the SORC and the Station Superintendent; however, the Station Superintendent shall have responsibility for resolution of sur.: disagreements pursuanc to 6.1.1 above.

RECOR05 The 50RC shall maintain written minutes of each meeting and copies 6.5.2.8 shall be provided to the Vice President Nuclear Operations and Chairman

-1 I

of the Site Nuclear Review Soard.

6.5.3 NUCLEAR REVIEW BOARD (NRB)

FUNCTION 6.5.3.1 The NRE 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 instrunentation and control e.

f.

radiological safety mechanical and electrical engineering g.

l Amendnent Mc. 75, )d, ffi, 85 6-9

ADMIN!$TRATivE CONTROLS REVIEW 6.5.3.7 The NRS shall review:

The safety evaluation for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provision a.

of Section 50.59, 10 CFR. to verify that such actions did not constitute an unreviewed safety question.

Proposed changes to procedures, equipment or systems which involve b.

an unreviewed safety question as defined in Section 50.59,10 CFR, Proposed tests or experiments which involve an unreviewed safety c.

question as defined in Section 50.59,10 CFR.

Proposed changes in Sections 1.0 - 5.0 of these Technical Specifi-d.

cations or licenses, Violations of applicable statutes, codes, regu1Ittons, orders, Technical Specifications license requirements, or of internal e.

procedures or instructions having nuclear safety significance._

Significant operating abnormslities or deviations from normal f.

and expected performance of plant equipment that affect nuclear safety.

REPORTABLE OCCURRENCE, as defined in Sections 6.9.1.7, 6.9.1.R

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g.

and 6.9.1.9.

Indications of a significant unanticipated deficiency, affecting h.

nuclear safety, in some aspect of design or operation of safety related structures, systems or components.

1.

Reports and meetings minutes of the PORC.

AUD*TS Audits of facility activities shall be perfertec under the cogni:ance 5.5.3.8 of tne NRB. These audits shall encompass:

tid The conformance of facility operation to all provisions conta:

a.

within the Technical Specifications and applicable license conditions at least once per year.

6-11 Amendment No. /, 85

ADMINISTRATIVE CONTROLS AUTHORITY 6.5.4.9 The SNRS report to and advise the Senior Vice President Nuclear Engineering and Operations on those areas of responsibility specified in Sections 6.5.4.7 and 6.5.4.8.

RECORDS 6.5.4.10 Records of SNR3 activities shall be prepared, approved, and distributed as indicated below:

Minutes of each SNRB meeting shall be prepared, approved ~, and '

a.

forwarded to the Senios Vice President Nuclear Engineering and Operations within 14' days following each meeting, b.

Reports of reviews encompassed by Section 6.5.4.7 above, shall be prepared, approved, and forwarded to the Senior Vice President Nuclear Engineering and Operations within 14 days following completion of the review.

c.

Audit reports encompassed by Section 6.5.4.8 above, shall be forwarded to the Senior Vice President Nuclear Engineering and Operations and to the managenent positions responsible for the areas audited within 30 days after completion of the audit.

6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:

a.

The Commission shall be notified and/or a report subnitted pursuant to the requirements of Specification 6.9.

b.

Each REPORTABLE OCCURRENCE Report requiring 24-hour notifica-tion to the Commission shall be reviewed by the PORC and submitted to the NRB and the Vice President Nuclear Operations.

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is viola ted :

a.

The unit shall be placed in at least HOT SHUTDOWN within two hours.

MILLSTONE - UNIT 1 6-15 AmendmentNo.1/,g,f4,)W,((.

t ADMINISTRATTVE CONTROLS SAFETY LIMIT V!0LATION (Continued)_

b.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Vice President Nuclear Operations and the NRB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

A Safety Limit Violation Report shall be prepared. The report shall c.

be reviewed by the PORC. 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.

The Safety Limit Violation Report shall be submitted to the Conynission d.

the NRB and the Vice President Nuclear Operations within 14 days of l

the violation.

~

6.8 PROCEDURES Written procedures shall be established, implemented and maintained

6. 8.1 covering the activities referenced below:

The applicable procedures recomended in Appendix "A" of Regulatory a.

Guide 1.33, November 1972.

b.

Refueling operations.

Survefllance activities of safety related equipment, c.

d.

Security Plan implementation.

Emergency Plan implementation.

e.

f.

Fire Protection Program implementation.

Each procedure and a[ninistrative policy of 6.8.1 above, and changes 6.8.2 thereto, shall be reviewed by the PCRC/SCRC, as applicable, and approved by the Unit Superintendent / Station Suoerintendent prior to imoleroentation and reviewed periodically as set forth in each document.

Anendment No. M.2(, 34,

, 85 16 I

A0MINISTRATIVE CONTROLS l

6.9.1.3 Startup reports shall be submitted within (1) 90 days following com;1etion of the startup test program, (2) 90 days following resumption or co-ence. ent cf commercial power operation, or (3) 9 months following initial criticality, wnichever is earliest.

If the Startup Report does not cover all three events (i.e., initial criticality, completion of l startu; test program, and resumption or commencement of commercial power le: era tier), supplementary reports shall be submitted at least every three onths until all three events have been completed.

l ANv)Pc Rio0tT51#

6.9.1.4 Annual reports covering the activities of the unit as described telow fer the previous calendar year shall be submitted prior to March I of each year. The initial report shall be submitted prior to March 1 of tr.e yea-following initial criticality.

6.9.1.5 A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr an ding to work andjobfunctions,g,theirassociatedman-remexposureaccor e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (described mainten-ance), waste processing and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD or film badge measurements. Small exposures totalling less than 20% cf the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

t

t/

A single submittal may be made for a multiple unit station. The submittel should combine those sections that are common to all units t

at the station.

2r This tabulation supplements the requirements of 120.407 of 10 CFR Pa rt 20.

i Amendment No. 24, 43, 85 6-18

[p** " %o, UNITED STATES x

/ ',

NUCLEAR REGULATORY COMMISSION j

! 1 W ASHINGTON, D. C. 20555 e

o e7 NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE HARTFORD ELECTRIC LIGHT COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET N0. 50-336 MILLSTONE NUCLEAR POWER STATION, UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 78 License No. DPR-65 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee) dated February 24, 1982, 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 for 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; l

C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health I

and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and i

E.

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

DESIGNATED ORIGINAL L

( Qmpo}

b b'MIA-Certified By -

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, 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-65 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.78, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

The license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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c,-

obebtA. Clark, Chief

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Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

June 25, 1982

ATTACHMENT TO LICENSE AMENDMENT NO. 78 FACILITY OPERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Delete Page Insert Pr.ge 6-1 6-1 6-2 6-2 6-4 6-4 6-5 6-5 6-6 6-6 6-7 6-7 6-9 6-9 6-15 6-15 6-16 6-16

7 g

i 6.0 ADMINISTRATIVE LONTROLS 6.1 RFSPONSIBILITY 6.1.1 The Station Superintendent shall be responsible for overall operation of the Millstone Station Site while the Unit Superintendent shall be responsible for operation of the unit. The Station Superintendent and Unit Superintendent shall each delegate in writing the succession to these responsibilities during l

their absence.

6.2 ORGANIZATION e

OFFSITE 6.2.1 The offsite organization for. facility management and technical support.

shall be as shown on Figure 6.2-1.

FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figure 6.2-2 and:

a.

Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

b.

At least one licensed Operator shall be in the control room when fuel is in the reactor.

c.

At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips, d.

An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.#

e.

All CORE ALTERATIONS after the initial fuel loading shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

f.

A site Fire Brigade of at least 5 members shall be maintained onsite at all times.# The Fire Brigade shall not include 2 members of the minimum shif t crew necessary for safe shutdown of the unit or any personnel requi. red for other essential functions during a fire emergency.

6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the Health Physics Supervisor who shall meet or exceed the qualifications of Regulatory Guide 1.8, Revision 1, and (2) the Shif t Technical Advisor who shall have a Bachelor Degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.

  1. See Note on Page 6-4.

MILLSTONE - UNIT 2 6-1 Amendment No. 45, 66, 78

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TABLE 6.2-1 MIlllMUM SHIFT CREW COMPOSITIO!4 t.

er APPLICABLE MODES

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Does not include the licensed Senior Reactor _or Senior Reactor j

Operator Limited to Fuel Handling individual supervision CORE i

ALTERATIONS after the initial fuel loading.

  1. The above shift crew composition and the qualified health physics technician and/or fire brigade members of Section 6.2.2 may be less than the. minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence provided expeditious actions are taken to fill'the required positions.

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MILLSTONE-UNIT 2 6-4 Amendment No f6, 78 -

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i ADMINISTRATIVE CONTROLS 6.4 TRAINING l6.4.1 retraining and replacement training program for the facility i

staff shall be maintained under the direction of the Station Superintendent and shh11 meet or e.xceed the requirements and recommqndations of Section 5,5'of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.

[

6M.2 A training program for the Fire Brigade shall be maintained under the direction of the Training Supervisor and shall meet or exceed the i

requirements of Section 27 of the NFPA Code-1975, except for Fire Brigade training sessions whi-ch shall be held at least quarterly.

6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)

FUNCTION 6.5.1.l The PORC shall function to advise the Unit Superintendent on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The PORC shall be composed of the:

Chairman:

Unit Superintendent

~~

1 l

Vice Chairman

& Member:

Operations Supervisor Member:

Maintenance Supervisor Member:

Instrument and Control Supervisor Member:

Reactor Engineer Member:

Engineering Supervisor or Startup Supervisor

  • Member Station Services Superintendent or General Services Supervisor or Quality Services Supervisor or Radiological Services Supervisor Member:

Staff Engineer **

ALTERNATES 6.5.1.3 Alternate members shall be appointed in writing by the PORC Chairman to serve on a temporary basis; however, no more than two alternates shall participate in PORC activities at any one time.

  • When position is staffed.
    • The Staff Engineer member of the PORC shall have an academic degree in engineering of physical science field; and in addition, shall have a minimum of five years technical experience, of which a minimum of three years shall be in the nuclear power plant industry.

MILLSTONE - UNIT 2 6-5 Amendment No. 3E, AE, EA, 78

ADMINISTRAT1.E CONTROLS MEETING FREQUENCY 6.5.1.4 The F,iRC shall meet at least once per calendar month and as convened by the PORC Chairman.

OUORUM 6.5.1.5 A quorum of'the PORC shall consist of the Chairman or Vice Chairman or Station Superintendent and four members including alternates.

RESPONSIBILITIES 6.5.1.6 The PORC shall be responsible for:

Review of 1) all procedures, except common site procedures, a.

required by Specification 6.8 and changes thereto, 2) any other proposed procedures or changes thereto as determined by the Unit Superintendent to affect nuclear safety.

b.

Review of all proposed tests and experiments that affect nuclear safety, c.

Review of all proposed changes to Sections 1.0 - 5.0 of these 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 preparation and forwarding of a report covering evaluation and recommendations to prevent recurrence to the Vice President fluclear Operations and to the Chairman of the f.

Review of events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission.

g.

Review of facility operations to detect potential safety hazards.

h.

Performance of special reviews and investigations and reports thereon as requested by the Chairman of the Nuclear Review Board.

i.

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.

MILLSTONE - UNIT 2 6-6 Amendment No. 79, R$, 95, 78

4 ADMINISTRATIVE CONTROLS 1

AUTHORITY 6.5.1.7 The PORC shall:

Recommend to the Unit S0perintendent written approval or a.

disapproval of items considered under 6.5.1.6(a) through (d) above.

A i

b.

Provide immediate written notification to the Station Superin-tendent, Vice President Nuclear Operations and the Chairman of.the Nuclear Review Board of disagreement between the PORC and the Unit Superintendent; however, the Unit Superintendent shall have responsibility for resolution of such disagreements i

pursuant to 6.1.1 above.

RECORDS 6.5.1.8 The PORC shall maintain written minutes of each meeting and copies shall be Drovided to the Station Superintendent, Vice i

President Nuclear Operations and Chairman of the Nuclear Review Board.

6.5.2 SITE OPERATIONS REVIEW COPNITTEE (SORC)

{

1 FUNCTION 6.5.2.1 The SORC shall function to advise the Station Superintendent on all matters related to nuclear safety of the entire Millstone Station Site.

I COMPOSITION 6.5.2.2 The SORC shall be composed of the:

Chairman:

Station Superintendent Member:

Unit 1 Superintendent Member:

Unit 2 Superintendent Member:

Unit 3 Superintendent Member:

Designated Member of Unit 1 PORC Member:

Designated Member of Unit 2 PORC Member:

Designated Member of Unit 3 PORC or t

Unit No. 3 Operations Supervisor Member:

Station Services Superintendent MILLSTONE - UNIT 2 6-7 Amendment No. 79, 28, /lff, 78

ADMINISTRATIVE CONTROLS ALTERNATES 6.5.2.3 Alternate members shall be appointed in writing by the 50RC Chairman to serve on a temporary basis; however, no more than two alternates shall participate in 50RC activities at one time.'

MEETING FREQUENCY 6.5.2.4 The 50RC shall meet at least once per six months and as convened by the 50RC Chairmars.'

~

~ ~ ~

QUORUM 6.5.'2.5 A quorum of the SORC shall consist of the Chainnan and four members including alternates.

RESPONSIBILITIES 6.5.2.6 The SORC shall be responsible for:

a.

Review of 1) all coninon site procedures required by Specifi-cation 6.8 and changes thereto, 2) any other proposed procedures or changes thereto as determined by the Station Superintendent l

to affect site nuclear safety.

b.

Review of all proposed changes to Section 6.0 " Administrative Controls" of these Technical Specifications.

c.

Performance of special reviews and investigations and reports as requested by the Chainnan of the Site Nuclear Review Board, d.

Review of the Plant Security Plan and implementing procedures and shall submit changes to the Chairman of the Site Nuclear Review Board.

e.

Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Chairman of the Site Nuclear Review Board.

f.

Review of all common site proposed tests and experiments that affect nuclear safety.

g.

Review of all common site proposed changes or modifications to systems or equipment that affect nuclear safety.

MILLSTONE - UNIT 2 6-8 AmendmentNo.[$,45

ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued) h.

Render determinations in writing or meeting minutes with regard to whether or not each item considered under 6.5.2.6(a) through (g) above constitutes an unreviewed safety-question.

AUTHORITY 6.5.2.7 The SORC shall:

a.

Recommend to the Station Superintendent written approval or disapproval in meeting minutes of items considered under 6.5.2.6(a) through (g) above.

b.

Provide immediate written notification or meeting minutes to the Vice President Nuclear Operations and the Chairman of the Site Nuclear Review Board of disagreement between the 50RC and the Station Superintendent; however, the Station Superintendent shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

RECORDS i

6.5.2.8 The SORC shall maintain written minutes of each meeting and l

copies shall be provided to the Vice President Nuclear Operations l

dnd Chairman of the Site Nuclear Review Board.

6.5.3 NUCLEAR REVIEW BOARD (NRB)

FUNCTION 6.5.3.1. The NRB 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 f.

radiological safety g.

mechanical and electrical engineering MILLSTONE - UNIT 2 6-9 Amendment No. 28, 47, 78

o ADMINISTRATIVE CONTROLS C0 POSITION 6.5.3.2 The Chairman, cembers and alternate members of the NRB shall be appointed in writing by the Senior Vice President, Nuclear Engineering and l

Operations, and shall have an aca'demic degreee in an. engineering or physical science field; and, in addition, shall h' ave a minimum of five years technical experience, of which a minimum of three years shall be in their respective fields of expertise., No more than two alternates shall participate as voting members in NRB activities at any one time.

i CONSULTANTS 6.5.3.3 Consultants shall be utilized as determined by the NRB Chairman to provide expert advice to the NRB.

MEETING FREQUENCY 6.5.3.4 The NRB shall meet at least once per calendar quarter during the initial year of facility operation following fuel loading and at least once per six months thereafter.

QUORUM 6.5.3.5 The minimum quorum of the NRB necessary for the performance of the NRB review and audit functions of these technical specifications shall consist of the Chairman or his designated alternate and at least four members including alternates. No more than a minority of the quorum shall have line responsibility for operation of the facility.

f

  • MILLSTONE - UNIT 2 6-10 Amendment No.19, 45

e ADMINISTRATIVE CONTROLS AUTHORITY 6.5.4.9 The SNRB report to and advise the Senior Vice President Nuclear Engineering and Operations on those areas of responsibility specified in Sections 6.5.4.7 and 6.5.4.8.

RECORDS e

6.5.4.10 Records of SNRB activities shall be prepared, approved, and distributed as indicated below:-

a.

111nutes of each SNRE meeting shall be prepared, approved, and forwarded to the Senior Vice President Nuclear Engineering and Operations within 14 days following each meeting.

b.

Reports of reviews encompassed by Section 6.5.4.7 above shall be prepared, approved, and forwarded to the Senior Vice President Nuclear Engineering and Operations within 14 days following completion of the review.

c.

Audit reports encompassed by Section 6.5.4.8 above shall be fonvarded to the Senior Vice President Nuclear Engineering and Operations and to the management positions responsible for the areas audited within 30 days after completion of the audit.

6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:

a.

The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.

b.

Each REPORTABLE OCCURRENCE Report requiring 24-hour notifica-tion to the Commission shall be reviewed by the PORC and submitted to the NRB and the Vice President Nuclear Operations.

l

, ; 6. 7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a.

The unit shall be placed in at least HOT STANDBY within one hour.

MILLSTONE - UNIT 2 6-15 Amendment No. 19, #5, 64, 78 w.

ADMINISTRATIVE u0NTROLS gfD LIMIT VIOLATION (Continu_e_d) t.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour.

The Vice President

~

Nuclear Operations and the NRB shall be notified Jith'in,24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

l A Safety Li,mit Violation Report shall be prepared.

The report c.

shall be reviewed by the PORC.

This report shall describe (1) applicable circumstances preceding the violation, (2) effects l

of the violation upon facility components., systems or structures, I

and (3) corrective action taken to prevent recurrence.

d.

The Safety Limit Violation Report shall be s'u'bmitted'to the Commission, the NRB and the Vice President Nuclear ~ ~

Operations within 14 days of the violations.

6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

a.

The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November 1972.

b.

Refueling operations.

c.

Surveillance activities of safety related equipment, d.

Security Plan implementation.

e.

Emergency Plan implementation.

f.

Fire Protection Program implementation.

6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the PORC/50RC, as applicable, and approved by the Unit Superintendent / Station Superintendent prior to implementation and reviewed periodically as set forth in each document.

MILLSTONE - UNIT 2 6-16 Amendment No. 7E, 35, AB, 78 m

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