ML20069F018
| ML20069F018 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/07/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20069F020 | List: |
| References | |
| NUDOCS 8209270431 | |
| Download: ML20069F018 (10) | |
Text
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e UNITED STATES
[
g NUCLEAR REGULATORY COMMISSION g
j WASHINGTON, D. C. 20555 Y
4 PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILADELPHIA ELECTRIC COMPANY LELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 S,.LEM NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 46 License No. DPR-70 1.
The Nuclear Regulatory Commission (the Commission) has found that:
~
A.
The application for amendment by Public Service Electric and Gas Company, Philadelphia Electric Company, Delmarva Power ar.d Light Company and Atlantic City Electric Company (the licensees) dated October 23, 1981, 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 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; D.
The issuance of this amendment will not be inimical co 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 annd all applicable require,ments have been satisfied.
1 8209270431 820907 PDR ADOCK 05000272 P
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-70*is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 46, 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.
~
F0fTHENUCLEARREGULATORYCOMMISSION b
1 L
t 4A f
' Operating Reacto Branch No. 1 Division of Lice ng
Attachment:
Changes toithe Technical Specifications Date of Issuance: September 7,1982 e
i
ATTACHMENT TO LICENSE AMENDMENT N0. 46 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET N0. 50-272 Revise Appendix A as follows:
Remove Pages Insert Pages 6-4 6-4 6-4a 6-4a 6-4b
,T O
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TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION SALEM UNIT 1 WITH UNIT 2 IN MODES 5 OR 6 OR DE-FUELED POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION MODES 1, 2, 3 & 4 MODES 5 & 6 a
a SS l
y a
SR0 l
none R0 2
1 D
A0 3
2 STA 1
none Maintenance 1
none Electrician WITH UNIT 2 IN MODES 1, 2, 3 OR 4 l
POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION l
MODES 1, 2, 3 & 4 MODES 5 & 5 a
a SS l
y a
SRO l
none R0 2-1 c
A0 3
y a
STA l
none a
Maintenance l
none Electrician 1
a/
Individual may fill the same position on Unit -2 b/
One of the two required individuals may fill the same position on Unit 2., such that there are a total of three A0s for both units.
c/
One of the three required individuals may fill the same position on Unit.2,-such that there are a total of five A0s for both units.
SALEM - UNIT 1 6-4 i
Amendment No. 46
TABLE 6.2-1 (Continued)
- Shift Supervisor with a Senior Reactor Operators License on Unit 1 Individual with a Senior Reactor Operators License on Unit 1 SR0 RO Individual with a Reactor Operators License on Unit 1 Auxiliary Operator A0 STA - Shift Technical Advisor Except for the Shift Supervisor, the Shift Crew Composition may be one less than the minimum requirements of Table 6.2.1 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 on-duty shift crew members provided immediate action is taken to restore the Shift Crew Composition to within the minimum requirements of Table 6.2-1.
This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.
During any absence of the Shift Supervisor from the Control Room while the unit is in MODE 1, 2, 3 or 4, an individual (other than the Shift Technical Advisor) with a valid SR0 license shall be designated to assume the Control Room command function.
During any absence of the Shift Supervisor from the Control Room while the unit is in MODE 5 or 6, an individual with a valid R0 license (other than the Shift Technical Advisor) shall be designated to assume the Control Room command function.
l SALEM - UNIT l-6-4a Amendment No. 46
6.2.3 SHIFT TECHNICAL ADVISOR 6.2.3.1 The Shift Technical Advisor shall serve in an advisory capacity to the Shift Supervie 3r on matters pertaining to the engineering aspects assuring safe operation of the unit.
6.2.3.2 The Shift Technical Advisor shall have a bachelor.'s 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.
i i
1 SALEM-UNIT 1 6-4b Amendment No. 46
o UNITED STATES g
[
g NUCLEAR REGULATORY COMMISSION
^j WASHINGTON, D. C. 20555
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PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET N0. 50-311 SALEM NUCLEAR GENERATING STATION, UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.11 License No. DPR-75 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Public Service Electric and Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated October 23, 1981, 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; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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; 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 E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comissior3's regulations annd all applicable requirements have been satisfied.
m
. 2.
Accordingly, the license is amended by changes to the Technical Specifice. ions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.11, 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 NUCL,AR REGULATORY COMMISSION
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lJUL lhh teVen A.
arga, hie
/ Operating Reactors r inch No.1 Division of Licensi
Attachment:
Changes to the Technical Specifications Date of Issuance: September 7,1982 o
ATTACHMENT TO LICENSE AMENDMENT NO.11 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET N0. 50-311 Revise Appendix A as follows:
Remove Page Insert Page 6-6 6-6 e
ADMINISTRATIVE CONTROLS 6.2.3 SAFETY REVIEW GROUP (SRG)
FUNCTION 6.2.3.1 The SRG shall function to examine plant operating characteristics, NRC issuences, industry advisories, Licensee Event Reports and other sources which may indicate areas for improving plant safety.
COMPOSITION 6.2.3.2 The SRG shall be composed of at least five dedicated, full-time engineers located onsite.
RESPONSIBILITIES 6.2.3.3 The SRG shall be responsible for maintaining surveillance of plant activities to provide independent verification
- that these activities are performed correctly and that human errors are reduced as much as practical.
AUTHORITY-6.2.3.4 The SRG shall make detailed recommendations for revised procedures, cquipment modifications, or other means of improving plant safety to the General Manager-Licensing and Environment.
6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall serve in an advisory capacity to the Shift Supervisor on matters pertaining to the engineering aspects assuring safe operation of the unit.
6.2.4.2 The Shift Technical Advisor shall have a bachelor's 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.
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 and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, except for the Radiation Protection Engineer who shall meet or exceed the cualifications of Regulatory Guide 1.8, September 1975.
6.4 TRAINING l
6.4.1 A retraining and replacement training program for the facility staff shall be coordinated by each functional level manager (Department Head) at the I
facility and maintained under the direction of the Training Manager and shall i
meet or exceed the requirements and recommendations of Section 5.5 of ANSI l
N18.1-1971 and Appendix "A" of 10 CFR Part 55 and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry cperational experience.
"Not responsible for sign-off function.
SALEM - UNIT 2 6-6 Amendment No. 11 i
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