ML20147E859
| ML20147E859 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Haddam Neck, 05000000 |
| Issue date: | 02/23/1988 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20147E772 | List: |
| References | |
| TAC-66323, TAC-66592, NUDOCS 8803070173 | |
| Download: ML20147E859 (23) | |
Text
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00hNECTIC01 YAhkEE ATOMIC POWER COMPANY DOCKET NO. 50-?l3 EACDAM NECK PLANT AFEhtr.EN1 10 F ACILIT) 0FERATING LICEhSE Amendment No.100 License Nc. [FR-61
- 1. The L'uclear Regulatcry Corr.ission (the Corrnission) has found that:
A. The applicatior. fer arendnent by Connecticut Yankee Atorr.ic Fower Conpany (tte licer.ste) dated September ?a.1967, cor. plies with the standards and requirerents of the Atenic Energy Act of 195a, as
- anended (the Act) and the Cormission's rules and regulations set forth in 10 CFR Chapter I; E. The facility will operate in confomity with the applicaticri, the previstoris of the Act, and the rules ud regulations of the Corr.ission; C. There is reasonable sssurance (1) that the activities authorized by this an4ndr(nt can be conducted without endangering the health and safety of the public, ard (ii) that such activities will be conducted in cor.pliar.ce with the Corrsission's regulations; C. Tht issuarce of this anendment will nct be intraical to the copron defense and security or to the health and safety of the r>ublic; and E. The issuance of this arendnent is in accordance with 10 CFR Part 51 of the Cocrission's regulations and all applicable requirerrents have been satisfied.
8803070173 080223 3 DR ADOCK 050
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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-61 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.100, are hereby incorporated 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 Joh Stolz, Director o Pr ject Directorate I-4 vision of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 23, 1988
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ATTACHVENT -TO LICENSE AMENDMENT N0J00 FACIL'11Y OPERATING LICENSE NO. DPR-61 DOCKET NO. 50-713 Replace the following page of the Appendix A Technical Specifications with the enclosed page as indicated. The revised page is identified by aniendrent number and contain vertical lines indicating the'ereas of change.
Rer.cVe Insert 6-li 6-12
r W 2-ADMINISTRATIVE CONTROLS 6.5.2.9 Records of NRB activities shall.he prepared, approved and distributed as indicated belows
- a. Minutes of each NRB meeting shall be prepared, approved ano
- forwarded to the Senior Vice-President-Nuclear Engineering and Operations within 14 days following each meeting.
- b. Reports of reviews encompassed by Section 6.5.2.6 above, sa!! be prepared, approved and forwarded to the Senior Vice President-Nuclear Engineering and Operations within 14 days following completion of the review.. NRB minutes may be used for. this purpose,
- c. Audit reports encompassed by Section 6.5.2.7 above, 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.
6-12 Amendment No.100
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- [pe rsog$c, UNITED STATES ~
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AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.14 License No. OPR-21
- 1. The Nuclear Regulatory Commission (the Comission) has found that:
A. The application for amendment by the Northeast Nuclear Energy Company (the licensee) dated September 24, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as
~ amended (the Act) and the Comission'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 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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- 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. DPR-21 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.14 , are hereby incorporated 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 O .
e oh . Stolz, Directo Pr ject Directorate I-4 vision of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 23.1988
A"ANEkUP. LJ.cM1E,,AMppg!Op,,14 .
FACILITY OPERAT1hG LICENSE NO. DPR-21 DOCKET N0_.,50,,2,45 Replace the following page of the Appendix A Technical Specifications with the enclosed page as indicated. The revised page is identified by anendrent nur.ber and contains a vertical line indicating the area of change.
The corresperding overleaf page is also provided to r,aintain document cor.ple teres s .
Recove Insert 6-12 6-17 e
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e ADMINISTRJTIVE CONTROLS 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 six months and as convened by the NRB Chairman.
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. No more than a minority of the quorum shall have line responsibility for operation of the facility.
Review 6.5.3.6 The NRS shall review:
- a. The safety evaluation for 1) changes to procedures, equipment or
- systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question,
- b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question, as defined in Section 50.59, 10 CFR,
- c. Proposed tests or experiments which involve an unreviewed safety question, as defined in Section 50.59, 10 CFR.
- d. Proposed changes in Sections 1.0 - 5.0 of these technical specifications or licenses.
- e. Violations of applicable statutes, codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance,
- f. Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety,
- g. All REPORTABLE 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. . .
i l h. Indications of a significant unanticipated' deficiency, affecting l
nuclear safety, in some aspect of design or operation of safety related structures, systems or components.
Amendment No. 1 Millstone Unit 1 6-11 JAN 29 567
E l s
ADMINISTRATIVE CONTROLS
- 1. Report and meetings minutes of the PORC.
Audits 6.5.3.7 Audits of Unit activities shall be performed under the cognizance of the NR3. These audits shell encompass:
- a. The conforcance of Unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.
- b. Tne performance, training, and qualifications of the unit staff at least once per 12 months.
- c. The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems, or method of operation that affect nuclear safety, at least once per six months.
- d. Any other area of unit operation considered appropriate by the NR3 or the Senior Vice President Nuclear Engineering and Operations.
Authority 6.5 3.6 ine NES shall report to and advise the Senior Vice President Nuclear Engineering and Operations on those areas of responsibility specified in Sections 6.5.3.6 and 6.5.3 7. Meeting minutes may be used for this purpose.
, Records 6.5 3 9 Records of NR3 activities shall be prepared, approved, and distributed as indicated below:
- a. Minutes of each NR3 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 3.6 above, shall be prepared, approved and forwarded to the Senior Vice President Nuclear Engineering and Operations within 14 days following completion of the review. NRB Neeting Minutes may be used for this purpose. ,
- c. Audit reports encompassed by Section 6.5 3 7 above, 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.
1:
MILLSTONE UNIT 1 6-12 Amendment No. 14 l
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NORTHEAST NUCLEAR ENLkM CCP.PANY 3.h.E,,C,0,hp,E,0, Tit,UJ,,L1,GHT AND P,0gR COMPANY T H E K E ST E_R N, ,Pf,S S,A,C,kU_$_E l l S_E,L E ,C),RJp, ,0ft,P A,N Y DOCKET NO. 50-336 FILLSTONE NUCLEAR 00KER STA110h 3 UNIT NO. 2 APEhcPEh1 1(, FACILITY OFERATING LICENSE Ar.endrent No. 125 License No. DPP-65
- 1. The Nuclear Regulatory Cornission (the Cornission) has found that:
A. The applicati(ris for arendment by Northeast Nuclear Energy Corpary, et al. (tte licensee), dated September 24, 1987, and November 2, 1987 coFply with the standards and requirect.nts of the Atcric Energy Act cf leu, as anended (the Act) and the Consission's rules and regula-tiers set forth in 10 CFR Chapter I; B. The fecility will operate in conferrity with the applicatier, the provisions of the Act, and the rules and regulations of the Corrission; C. There is reasonable assurance (1) that the activities authorized
. ty this antodnent can be conducted without endar$ering the health and safety of the public, and (ii) that such activities will be cenducted in compliarce with the Cornission's regulations; C. The issuance of this erer.dnent will net be inimical to the comen defense and security or to the health and safety of the public; and E. The issuance of this enerdnent is in accordance with 10 CFR Part 51 of the Cornission's regulations and all applicable requirerer.ts han been satisfied.
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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. DPR-65-is hereby amended to read as follows:
(2) Technical' Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.125 , are hereby incorporated 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 f l F. Stolz, Director r jact Directorate I-4 ivision of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 23, 1988
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ATTACHMENT TO LICENSE AMENDMENT NO.125 FACILITY OPERATING LICENSE NO. OPR-65 DOCKET NO. 50-336 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 areas of change.
The corresponding overleaf pages are also provided to maintain document ,
completeness.
Remove Insert 3/4 3-52 3/4 3-52 3/4 3-57 3/4 3-57 3/4 3-58 3/4 3-58 6-12 6-12
l I TABLE 3.3-12 l
RADIDACTIVE LIQUID EFFLUENT MONITORING INSTRt#ENTATION l ,
l l Auum MINIftM f SETPOINT m INSTRISENT OPER*.8LE REQUIRED APPLICABILITY ACTION e
g 1. Gross Radioectivity Monitors Providing
- q Autonetie Terminetion of Relee,se l
- e. Clean Liquid Redneste Effluent Line 1 Yes 1
- b. Aereted Liquid Redunste Effluent
- Line 1 Yes 1
- c. Steen Generator Bleudoun Monitor or ***
Condenser Air Ejector Monitor 1** Yes 2 w
l 1 d. Condensate Polishing Facility.Weste ***
Neut S g 1 Yes 1 of
- 2. Gross Radioactiv1ty Monitors Rot Providing Amtesatic Terminetton of Release
^'
- e. Reector Building Closed Cooltag
- Water Moniterf 1 Yes, 3
- 3. Flow Rate Measurements .
'1
- 4 -
- e. Cloen Liguld Reduaste Effluent Line -
No y e-
- b. Aereted Liquid Redoeste Effluent
- r* = .
y '
Like 1 No 4
- c. Condensate Polishing Fact 11ty Weste Ik,-
- 4 Newt Susp Discharge Line 1 ,
, no *
- d. Dilution Water Flou ,
, ## NA
- MA
- e. Steam Generator Blowdown Line fff No ,
e TABLE 3 3-12 (continued)
RADIOACTIVE LIQUID EFFI.UENT MONITORING INSTRlWNTATION Table Notes
- - At all times - which means that channels shall be OPERARif. and in service on a continuous, uninterrupted basis, except that outages are permitted, for a m1ximum of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, for the purpose of maintenance and performance or required tests, checks, calibrations, or sampling. ,
- - Although both monitors are normally operable, only one is necessary as the activity measured by each can be related to the other, and both monitors are capable of automatically isolating the steam generation blowdown.
"' - Modes 1-5 and Mode 6 when pathway is being used except that outages are permitted for a maximum or 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for the purpose of maintenance and performance or required tests, checks, calibrations, or sampling. l
- - Since the only source or service water contamination is the reactor building closed cooling water, monitoring of the closed cooling water and conservative leakage assumptions will provide adequate -
control or service water effluents.
- - The dilution water is determined by the use of condenser cooling water and service water pump status.
Only those pumps actually discharging to the quarry at the time of release are included. Pump status is only reviewed for purposes of determining flows.
- - Determined by the use of valve curves and/or make up riow rates for the purpose or deterair.ing riows only. ,
NA - Not applicable.
3/4 3-52 Amendment No. [4.125 * -
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. l 4.
TABLE 3 3-13 RADIOACTIVE GASE0US EFFLUENT INSTRUMENTATION MINIMUM ALARM CHANNELS SETPOINTS INSTRUMENT OPERABLE REQUIRED APPLICABILITY ACTION
- 1. - MP2 STACK
- a. Noble Gas Activity Monitor 1 Yesses en 3
- b. Iodine Sa=pler 1 No en 2
- c. Particulate Sacpler 1 No " 2
- d. Stack Flow Rate Monitor 1 No se 3
- e. Sampler Flow Rate Menitor 1 No se 3
- 2. MP1 MAIN STACK
- a. Noble Gas Activity Monitor 1 Yesses se 5
- b. Iodine Sa:ple 1 No ** 2
- c. Particulate Sa=pler 1 No se 2
- d. Stack Flow Pate Monitor 1 Ko me 3
- e. Sampler Flow Rate Monitor 1 No se 3 3 WASTE GAS HOLDUP SYSTEM -
NOBLE GAS MONITOR PROVIDING AUTOMATIC TERMINATION OF RELEASE 1 Yes
- 4 8 - During waste gas holdup system discharge, se -
At all times which means that channels shall be OPERABLE and in service on a continuous, uninterrupted basis, except that outages are permitted for a maximum of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for the purpose of maintenance and performance of required tests, checks, calibrations, or sampling.
I
- - No automatic isolation features.
MILLSTONE - UNIT 2 3/4 3-57 Amendment No, yd4,125
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1.0 .
TABLE 3 3-13 (Continued)
ACTION STATEMENTS l
ACTION 1: With the number of channels OPERABLE less than required by the Minimum Channels GPERABLE requirements, effluent 731 eases via this pathway may continue provided that best efforts are made to repair the instrument and that grab samples are taken once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples ,
are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. l l
ACTION 2: With the number of channels OPERA 3LE less than required by the Minimum Channels OPERABLE requirements, effluent releases via this pathway may continue provided that best efforts are made to repair the instrument and that samples are continuously collected with auxiliary sampling l
equipment for periods of seven (7) days and analyzed for principle gamma emitters with half lives greater than 8 days within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after the end of the sampling period. Auxiliary sampling must be
, initiated within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of initiation of this ACTION statement.
ACTION 3: With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue proviced that the best efforts are made to repair the instrument and that the flow rate is estimated once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, ACTION 4: With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement:
Releases from the Millstone Unit 2 waste gas system may continue provided that best efforts are made to repair the instrument and that prior to initiating the release:
,' (a) At least two independent samples of the tank's contents are t analyzed; and l
(b) The original release rate calculations and discharge valve e lineups are independently verified by a second individual.
- Otherwise, suspend releases from the waste gas holdup system.
ACTION 5: With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, Mi>1 stone Unit 2 releases via the Millstone Unit 1 stack may continue provided that best efforts are made to repair the instrument and that grab samples are taken once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for gross radioactivity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. ,
Amendment No.1,$'4,125 MILLSTONE - UNIT 2 3/4 3-58
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ADi11NISTRATIVE CONTROLS f
REVIEW f i
6.5.3.6 The NRS shall review:
- a. The safety evaluations for 1) changes to procedures, equipment or systems, and 2) tests or experiments completed under the provisions of Section 50.59, 10 CFR, to verify that such actions did not g constitute an unreviewed safety question.
- b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
- c. Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
- d. Proposed changes in Sections 1.0 - 5.0 of these Technical Specifications or licenses.
- e. Violations of applicable statutes, codes, regulations, orders, ,
Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significarice. ls
- f. Significant operating abnormalities or deviations from ncrual and C expected performance of plant equipent that affect nuclear safety. ,
- g. All REPORTABLE EVENTS.
- h. Indications of a significant unnnticipated deficiency, affecting nuclear safety, in some aspect of design or operation of scfety related structures, systems or components,
- i. Reports and meeting. minutes of the PORC. ,
AUDITS 6.5.3.7 Audits of Unit activities shall be performed under the cognizance of the NRB. These audits shall encompass:
- a. The conformance of Unit operation to all provisions contained
~w ithin the Technical Specifications and applicable license conditions at least once per 12 months.
( MILLSTONE - UNIT 2 6-11 Amendment No. 9,$5,93,111.
ADMINISTRATIVE CONTROLS- .
A UDITS (Continued) b.
Th'e performance, training, and qualifications of the unit staff at ~ -
least once per 12 months.
c.
The results of actions taken to correct deficier.cies occurring in unit equipment, structures, systems, or method of operation that affect nuclear safety at least once per six months.
d.
' Any other area of unit operation considered appropriate by the NRB or the Senior Vice President Nuclear Engineering and Operations.
_A UTH ORITY 6.5.3.8 The NRB shall report to and advise the Senior Vice President Nuclear Engineering and Operations on those areas of responsibility specified in Sections 6.5.3.6 and 6.5.3.7. Meeting minutes may be used for this purpose.
RECORDS 6.5.3.9 Records . of NRB activities shall be prepared, approved, and distributed as indicated below:
a.
Minutes of each NRB 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 6.5.3.6 above, shall be prepared, appresed and forwarded to the. Senior Vice President Nuclear Engineering and Operations within 14 days '
completion purpose. of the review. NRB Meeting Minutes may be used for thisfollowing c.
Audit reports encompassed by Section 6.5.3.7 above, 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 af ter completion of the audit.
MILLSTONE UNIT 2 6-12 AmendmentNo.P[ffI,f(,)d,125
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NORTHEAST NUCLEAR ENERGY COMPANY, ET AL.*
DOCKET NO. 50-423
- MILLSTONE NUCLEAR POWER STATION, UNIT NO. 3
' AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.15 License No. NPF-49
- 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 September 24, 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 tne Act, and the rules and regulations of the Commission; C. There is reasonable tssuranc' (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; D. The issuance of this amendment will not be ininical to the common 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 requirenents have been satisfied.
!
- Northeast Nuclear Energy Company is authorized to act as agent and represent-ative for the following Owners: Central Maine Power Company, Central Vermont Public Service Corporation, Chicopee Municipal Lighting Plant, City of Burlington, Vermont, Connecticut Municipal Electric Light Company, Massachusetts l . Municipal Wholesale Electric Company, Montaup Electric Company, New England l Power Company, The Village of Lyndonville Electric Department, Western Massachusetts Electric Company, and Vermont Electric Generation and l Transmission Cooperative, Inc., and has exclusive responsibility and control l over the physical construction, operation and maintenance of the facility.
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- 2. Accordingly, the license is amended by changes.to the Technical Specifications as indicated in the attachment to this license 1 amendment, and paragraph 2.C.(2) of Facility Operating License !
No. NPF-49 is hereby amended to read as follows:
(2) Technical Specificttions The Technical Specifications contained in Appendix A, as revised through Amendment No.15 , are hereby incorporated 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 REGULAT RY COMMISSION l -
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Jo F. Stolz, Director oject Directorate I-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 23, 1988
t ATTACHVENT TO LICENSE AMENDMENT .N.O. 1_5_
FACILITY OPERA 11NG LICENSE NO. NPF-49 DOCKETNO.,5p,-9,3 Replace the following page of the Appendix A Technical Specifications with the enclosed page as indicated. The revised page is idertified by anendnent nur.ber and centains a vertical line indicating the area of change.
The' correspc:nding overleaf page is also provided to maintain docunent con.pletenes s .
Remove Insert 6-13 6-13 s
9 e, -
-- -, . .--r- - - , - - --
- e. .
C ADMINISTRATIVE CONTROLS RECORDS 6.5 3 9 Records of NR3 activities shall be prepared, approved, and distributed as indicated below:
- a. Minutes of each NR3 meeting shall be prepared, approved, and for-warded to the Senior Vice President-Nuclear Engineering and Opera-tions within 14 days following each meeting;
- b. Reports of reviews encompassed by Specification 6.5 3.6 shall be prepared, approved, and forwarded to the Senior Vice President-Nuclear Engineering and Operations within 14 days following completion of the review. NR3 Meeting Minutes may be used for this purpose;
- c. Audit reports encompassed by Specification 6.5.3 7 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.
6.5.t SITE NUCLEAR REVIEh' BOARD (SNR3)
FUNCTION 6.5.4.1 Tne SNR3 shall functien to provide independent review and audit of designated activities in the areas of:
- a. Nuclear power plant operations,
- b. Administration,
- c. Chemistry and radiochemistry,
- d. Quality Assurance practices, and
. e. Radiological safety.
COMPOSITION 6.5.4.2 The SNR3 shall consist of no less than six, nor more than nine members including the individual Millstone NR3 Chairman and the Station Superintendent.
The Chairman and members of the SNR3 shall be appointed in writing by the Senior Vice President-Nuclear Engineering and Operations, and shall have an academic degree in engineering or physical science field or hold a senior management position. In addition, they shall have a minimum of 5 years technical experience, of which a minimum of 3 years shall be in their respective field of expertise.
CONSULTANTS 6.5.4.3 Consultants shall be utilized as determined by the SNRB Chairman to
! provide expert advice to the SNR3.
l MIETING FREQUENCY 6.5.4.4 The SNR3 shall meet at least once per calendar year.
MILLSTONE - UNIT 3 6-13 Amendment No.15
e ADMINISTR ATIVE CONTROLS OUORUM 6.5.4.5 A quorum of SNRB shall consist of the Chairman or his designated .
alternate and four SNRB members. No more than a minority of the quorum shall have line responsibility for operation of the station.
REVIEW l
l 6.5.4.6 The SNRB shall reviews
- a. Proposed changes in Section 6.0 of these Technical Specifications or Licenses common to all mits.
I
- b. Any indication of an unanticipated deficiency In some aspect of design or operation of safety-related structures, systems or components common to a!! units.
- c. Reports and meeting minutes of the SORC.
AUDTTS .
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6.5.4.7 Audits of site activities shall be performed under the cognizance of the ;.
SNRB. These audits shall encompass: :
- a. The performance of activities required by the Quality Assurance .orogram to meet the criteria of Appendix 8,10 CFR Part 30, at least once per 24 months. ,
g
- b. The Site Emergency Plan and implementing procedures at least once per 24 months.* . . ,
- c. The Site Security Plan and implemeating procedu cs at least once per 24 months.*
- d. The Fire Protection Program and implementing procedures at least once per 24 months.
- e. 7he fire protection equipment and program implementation at least once per 12 months utilizing other a qualified offsite licensee fire protection ,
engineer or an outalde independent fire protection consultant. An ouulde independent fire protection consultant shall be used at least every third year.
- f. The performance of activities in accordance with the RADIOLOGICAL EFFLUENT MONITORING AND OFF5ITE DOSE CALCULATION MANUAL at least once per 24 months; l g. The performance of activities required by the quality control section of Regulatory Guide 1.21, Rev.1, June 1974, and Regulatory Guide 4.1, Rev.1, April 1973, at lease once per 12 months.
- Annual audits of the Emergency Plan and the Security Plan are also performed
' to satisfy the additional requirements of 10 CFR Part 30.54(t) and to CFR Part 7.40(d), respectively. These annual audits may be used to satisfy the requirements contained in the Technical Specifications.
6-14 Amendment No. 1 MILL 5 TONE - UNIT 5
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