ML20055C858
| ML20055C858 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 06/18/1990 |
| From: | Wessman R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20055C854 | List: |
| References | |
| NUDOCS 9006250267 | |
| Download: ML20055C858 (7) | |
Text
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'Y UNITED STATES
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'n NUCLEAR REGULATORY COMMISSION p.
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YANKEEATOMICELECTRICCOMPANJ DOCKET NO. 50 029 l
YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 132 License-No. DPR-3 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
A.
The application for amendment filed by Yankee Atomic Electric Company (the licensee) dated April-l2,1990, and April 20, 1990, 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 4
forth in 10 rFR Chapter I; B.
The facility will opente 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 set forth in 10 CFR Chapter I;
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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
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1 E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of
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the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as-indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-3 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.132, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
9006250267 900618 PDR ADOCK 05000029 P
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3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Tun Richard H Wessman, Director Project Directorate I-3 Division of Reactor. Projects I/II-Office of Nuclear Reactor Regulation l
Attachment:
- Changes to the Technical Specifications Date of Issuance:
June 18,1990 l
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i ATTACHMENT TO LICENSE AMENDMENT NO.132 FACILITY OPERATING LICENSE NO. DPR-3 DOCKET NO.50-029 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and
-i contain vertical lines indicating the area of change.
Remove Insert pg 6-2 pg 6-P 6-5 6-5 6-6 6-6 6-7 6-7
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i 5,6.M*ltal? n M miDROLE (Cont i nued )
y e.
ALL COPE ALTERATIONE after the initial fuel loading shall be directly_ supervised by either a licensed senior reactor operator or' senior reactor.cperator limited to fuel handlirig whc has no other concurrent, responsibilities during this operation, f.
A fire brigade of at least 5 members shall be maintained on-site at all times.
The fire brigade shall not include the minimum shif t crew necessary for safe shutdown of the plant, 2 licensed operators, or any personnel required for other essential fun:tions during'a fire emergency.
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Aomannstratawe procedures shall be developed and implemented to limit the working hours of the unit staff who perform safety-e'stcr ic n: t. ; ra :
e.g.,
ser;;/ reactar cperators, rea::.
operators,. health physicists, auxiliary operators, and key maintenance personnel, t
Adeouate shift coverage shall be maintained without rcutine heavy j
use of overtime.
The objective shall be to have operating personnel wor 6, on the average, an approximate 40-hour week while g
the olant is operating.
However, in the event that unforseen problems require substantial amounts of overtime to be used, or g
during extended periods of shutdown for refueling, major maintenance or major plant modifications, on a temporary basis, the following guidelines shall be followed:
- 1. '
An Individual should not be permitted to work more than 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> s str aight, ercluding shif t turnover time.
2.
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 49-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, all e :lucing shift turnover time.
2.
A break of at least B hours should be allowed between work periods, including shift turnover time.
I 4.
Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.
Any deviation from the above guidelines shall be authorized by the Plant Superintendent or his delegated representative, or higher levels of management, in accordance with established.orocedures
- t.
and with documentation of the basis for granting the deviation.
Controls shall be included in the procedures such that individual 1
Lt overtine shall be reviewed monthly by the Plant Superintendent or' his delegated representative to assure that excessive hours have not_been assigned.
Routine deviation from the above guidelines is not authorized.
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VANMEE-ROWE 6-2 Amendment No.,4(, p(,,91, 132
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I TABLE 6.2-1 NINIMUM SHIFT M CDNPDSIT1DN #'
LICENSE CATEGORY APPLICABLE MODES i
QUALIFICAT3DNS 1, 2,3&4 5&6 SRO '
2 le RO 2
1 k
Non-Licensed Auxiliary 2**
1 Operator Shift Technical Advisor 1-None Required l
Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supervising CORE ALTERATIONS after the initial fuel' loading.
One additional noi.- 'iransed operator is required for. MODE 2 except when restarting within foui hours of a shutdown for which the cause has been clearly established.
Shift crew composition 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 of duty shift crew members provided immediate.
action is taken to restore the shift crew composition to within I
L the minimum requirement of Table-6.2-1..
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Amendment No. pd, jf[' 132 YANKEE Rowe 6-5
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([MINISTRaiIVE'CONTPCLF
.6,3 FAtiLITY STAFF OUALIFICATIONS d.I. ! Ee:h 'me rter cf-the f.:llity. staff listed below shall meet or e.ceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the Shif t Technical Advisor who shall have a bachelor 's degree or = equivalent in a' scientific or engineering. discipline'with specific training In plant
, design, and responte and analysis of the plant for transients and accidents.
J and the Radiaison Protectior. Marager who shall meet the mininium qualifications
' 4-of Regulatory Guide 1.8, Revision 1.
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Ture-!ete "r
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Assistant Plant Superintendent I
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c.-
Plant Chemistry Manager j
d.
Plant Operations Manager e.
Reactor Engineering Manager f.
Plant Maintenance Manager g.
Maintenance Suoervisor h.
Instrument and Control Supervisor i.
Shift. Supervisors Lj.
Radiation Protection Manager L.
Technical Director 1.
dntit lecnn4tti' Aa v'isor c
m.
Technical Services Manager t.
Maintenance Support Supervisor
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Operations Support Supervisor l
6.4 TRAINING
~6.4.1.A retraining and replacement-training program for the facility NRC licenses staff sha!! be maintained under the direction of the Treining Manage *
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and shall meet or exceed the requirements and recommendations of Section 5.5
'of ANSI N10.1-1971 and Apoendix "A"'of 10 CFR Part 55.
.l 6.4.2 A training program for the Fire Brigade shall be maintained under the direction of a member of the plant. staff appointed to perform the. duties of Fire Protection Coordinator and shall meet or exceed the requirements of
'Sectico 27 of the NerA Code-1975, except for Fire Brigade trainin; sessions which shall be held at least quarterly.
Amendment No. N. N.,PI, 132 YANMEE RDWE 6-6 1
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3.C.hlNISTRATIVE CONTROLE
-c 6.9 REVIEW AND AUDIT 6.5.1 PLANT OPERATION REVIEW COMMITTEE FUNCTION 6.5.1.1 The Plant Operation Review Committee (PORC) shall function to advise the Plant Superintendent or, all matters related to nuclear safety.
COMPOSITION l
6.5.1.2 The Plant Operation Review Committee shall be composed of the :
Chairman:.
Plant Superintendent Vice Chairman:
Assistant Plant Superintendent Vice Chairman:
Technical Director Menttr -
riant 0?eretioris Mar.sger Member:
Plant Maintenance Manager Membert.
Reactor Engineering Manager Member:
Plant Chemistry Manager Member:
Instrument and Control Superviser Member Radiation Protection Manager l
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Member:
Maintenance Supervisor l
Member:
Technical Services Manager Memb er. :
Maintenance Support Supervisor Member:
Operations Support Supervisor l
AtTERNATE5 l
1 6.5.1.3 All alternate members shall be appointed in writing by the PORC-p Chairman to serve on a temporary basis; however, no more than two alternates, shall participate as voting members in PORC activities or count toward a PORC ouorum at any one time.
-MEETING FREQUENCY i
6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairnan or Vice Chairman.
.DUORUM
~6.5.1.5 A ouerum of the FORC shall consist of a minimum of six people as l
.follows:
a.
.The Chairman or Vice Chairman plus five members, or b.
The Chairman and Vice Chairman plus four members, or l
0 c.
The Chairman and two Vice Chairmen plus three members, or d.
The two Vice Chairmen plus four members.
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RESPONEIBILITIES
!l 6.5.1.L The Plant Operation Review Committee shall be responsible fort i
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a.
Review of:
- 1) all procedures required by Specification 6.8 and charges thereto, 2) any other proposed procedures or changes l
thereto as determined by the Plant Superintendent to affect nuclear safety.
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/,%'IN Amendment No, p!,d,
YANUEE-ROWE-6-7 7
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