ML20133P365
| ML20133P365 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 08/01/1985 |
| From: | Butcher E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20133P368 | List: |
| References | |
| NUDOCS 8508140275 | |
| Download: ML20133P365 (10) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION n
-l W ASHINGTON, D. C. 20655
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BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.106 License No. DPR-53 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Baltimore Gas & Electric Company (thelicensee)datedMay 10, 1985 as supplemented by letter dated May 31, 1985, 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 (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (11) 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.
eQOh e
2.
Accordingly, the license is amended by changes to the Technical l
Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-53 is hereby amended to read as follows:
l (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.106, 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
$h l
Edward J. Butcher, Acting Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: August 1, 1985 I
ATTACHMENT TO LICENSE AMENDMENT N0.106 FACILTIY OPERATING LICENSE N0. DPR-53 DOCKET NO. 50-317 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by amendment number and contains vertical lines indicating the area of change. The corresponding overleaf page is provided to maintain document completeness.
Remove Page Insert Page 6-5 6-5 l
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TABLE 6.2-1 (Continued)
- Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supervising CORE ALTERATIONS during fuel reloading.
- Assumes each individual is licensed on each unit.
- 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 accomodate unexpected absence of on duty shift crew members provided imediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2.1.
- The STA shall be qualified / serve as follows:
(1) With one unit in MODE 5 or 6, and the other unit in MODE 1, 2, 3 or 4, the SOL holder other than the Shift Supervisor shall serve as the STA.
(2) With one unit defueled and the other unit in MODE 1, 2, 3 or 4, the STA shall be an SOL holder in addition to the one 50L required.
(3) With both units in MODE 1, 2, 3 or 4, the STA shall be an SOL holder in addition to the two SOLs required.
As an alternative to the above, the STA may be an individual with the following minimum qualifications: 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.
CALVERT CLIFFS - UNIT 1 6-5 Amendment No. 53,105
l ADMINISTRATIVE CONTROLS 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 the Radiation Safety Engineer who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and (2) the Shift Technical Advisor who f
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.
6.4 TRAINING 4
l 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the General Supervisor - Training and Technical Services for the Nuclear Power Department and the General Suoervisor forl the Production Maintenance Department and shall meet or exceed the regiJirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix A" of 10 CFR Part 55, as applicable.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the General Supervisor - Training and Technical Services and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975.
6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS AND SAFETY REVIEW COMMITTEE (POSRC)
FUNCTION i
6.5.1.1 The POSRC shall function to advise the Plant Superintendent on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The POSRC shall be composed of the:
Chairman:
Plant Superintendent flember:
General Supervisor - Operations Member:
General Supervisor - Electrical and Controls Member:
General Supervisor - Chemistry Member:
Principal Engineer - Plant Engineering Nuclear Member:
General Supervisor - Maintenance and Nodifications Member:
Pr,incipal Engineer - Incore Fuel Management Member:
General Supervisor - Radiation Safety Member:
General Supervisor - Training and Technical Services ALTERNATES l
6.5.1.3 All alternate members shall be appointed in writing by the POSRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in POSRC activities at any one time.
CALVERT CLIFFS - UNIT 1 6-6 Amendment No. H, 4, 8, 4I/ 85
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BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318 I
CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 2 t
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AMENDMENT TO FACILITY OPERATING LICENSE l
i Amendment No. 87 License No. DPR-69 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Baltimore Gas & Electric Company (thelicensee)datedMay 10, 1985 as supplemented by letter dated May 31, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's t
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.
Thereisreasonableassurance(i)thattheactivitiesauthorizedby l
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; i
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 i
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have i
been satisfied, j
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2.
Accordingly, the license is amended by changes to the Technical l
Specifications as indicated in the attachment to this license amendment.
l and paragraph 2.C.2 of Facility Operating License No. DPR-69 is hereby l
amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.~87 are hereby incorporated in the license.
The Itcensee 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 C0FNISSION l
Edward J. Bu'tcher, Acting Chief Operating Reactors Branch #3 l
Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: August 1, 1985 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 87 FACILTIY OPERATING LICENSE NO. DPR-69 DOCKET NO. 50-318 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by amendment number and contains vertical lines indicating the area of change. The corresponding overleaf page is provided to maintain document completeness.
Remove Page Insert Page 6-5 6-5 l
l IS
TABLE 6.2-1 (Continued)
- Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supervising CORE ALTERATIONS during fuel reloading.
- Assumes each individual is licensed on each unit.
- 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 accomodate 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.
- The STA shall be qualified / serve as follows:
(1) With one unit in MODE 5 or 6, and the other unit in MODE 1, 2, 3 or 4, the SQL holder other than the Shift Supervisor shall serve as the STA.
(2) With one unit defueled and the other unit in MODE 1, 2, 3 or 4, the STA shall be an SOL holder in addition to the one 50L required.
(3) With both units in MODE 1, 2, 3 or 4, the STA shall be an SOL holder in additicn to the two SOLs required.
As an alternative to the above, the STA may be an individual with the following minimum qualifications: 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.
CALVERT CLIFFS - UNIT 2 6-5 Amendment No. 36,87
ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifica-tions of ANSI N18.1-1971 for comparable positions, except for the Radiation Safety Engineer who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and (2) 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 response and a'nalysis of the plant for transients and accidents.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the General Supervisor - Training and Technical Services for the Nuclear Power Department and the General Supervisor forl the Production Maintenance Department and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55, as applicable.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the General Supervisor - Training and Technical Services and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975.
6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS AND SAFETY REVIEW COMMITTEE (POSRC)
FUNCTION 6.5.1.1 The POSRC shall function to advise the Plant Superintendent on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The POSRC shall be composed of the:
Chairman:
Plant Superintendent Member:
General Supervisor - OpertJons Member:
General Supervisor - Electrical and Controls Member:
General Supervisor - Chemistry itember:
Principal Engineer - Plant Engineering Nuclear tiember:
General Supervisor - Maintenance and Modifications Member:
Principal Engineer - Incore Fuel Management Member:
General Supervisor - Radiation Safety Member:
General Supervisor - Training and Technical Services ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the POSRC Chairman to serve on a tesprary basis; however, no more than two alternates shall participate as votng members in POSRC activities at any one time.
CALVERT CLIFFS - UNIT 2 6-6 Amendment No. 17, 26, 36, S ',68'
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