ML20237G622
| ML20237G622 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 08/21/1987 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20237G624 | List: |
| References | |
| NUDOCS 8709020337 | |
| Download: ML20237G622 (9) | |
Text
- oto* a'og'o UNITED STATES O
l' 3..scf[j NUCLE AR REGULATORY COMMISSION WASW NGTON, D. C. 20555 g-
-y POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET N0. 50-333 JAPES A. FITZPATRICK NUCLEAR POWER PLANT AMENDYENT TO FACILITY OPERATING LICENSE Amendment No.111 License No. DPR-59 1.
The Nuclear Reculatory Commission (the Commission) has found that:
A.
The applications f6F' amendment by Power Authority of the State of New York (the licensee) dated July 11 and October 27, 1986, and June 4,1987, comply 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 applications, 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 (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 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 requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.0.(2) of Facility Operating License No. DPR-59 is hereby amended to read as follows:
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(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.111, are hereby incorporated in the license. The licensee shall I
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, d obert A. Capra, Acting irector Project Directorate I-1 Division of Reactor Projects, 1/II
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 21, 1987 6
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UNITED 3TATES.
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NUCLEAR REGULATORY COMM13SIDM n
y WASHrWGTOW. D. C. 206%
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i TACPMENT TO LICENSE AMENDMENT NO. 313 l
FACILITY OPERATING LICENSE NO. DPR-59
. DOCKET NO. 50-333 j
Revise Appendix A as foliters:
Remove Paces Insert'Peoes vi vi
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247 l'47 247a 247a 248 248 260 P60 260a l
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JAFNPP LIST OF TABLES (CONT'D) vs
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Pace Table Title
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l 4.6-1 Comparison of the James A. FitzPatrick Nuclear 157 Power Plant Inservice Inspection Program to ASME Inservice Inspection Code Requirements 3.7-1 Process Pipeline Penetrating Primary Containment 198 4.7-1 Minimum Test and Calibration Frequency for 110 containment Monitoring Systems 211 4.7-2 Exception to Type C Tests l
260a 6.2-1 Minimum Shift Manning Requirements 6.10-1 Component Cyclic or Transient Limits 261 l
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1 l
Amendment No. ;H$, M, d, 111 vi 4
6.0 ADMINISTRATIVE CONTROLS Administrative Controls are the means by which plant operations are j
sub]ect to management control.
Measures specified in this section
]
provide for the assignment of responsibilities, plant organization, j
staf fing qualifications and related requirements, review and audit mechanisms, procedural controls and reporting requirements.
Each of l
these measures are necessary to ensure safe and efficient facility operation.
1 l
6.1 RESPONSIBILITY l
The Resident Manager is responsible for safe operation of the plant.
During periods when the Resident Manager is unavailable, the Superintendent of power will assume his responsibilities.
In the event both are unavailable, the Resident Manager may delegate this responsibility to other qualified supervisory personnel. The Resident Manager reports directly to the Executive Vice president-Nuclear Generation, as shown in Fig. 6.1-1.
6.2 PLANT STAFF ORGANIZATION
The plant staff organization shall be as shown in Figure 6.2-1 and:
1.
Each shift crew shall be composed of at least the minimum shif t crew composition shown in Table 6.2-1;
(
2.
An SRO or an SRO with a license limited to fuel handling shall directly supervise all Core Alterations. This person shall have no other duties during this time:
3.
A fire brigade of five (5) or more members shall be maintained on site at all times.
This excludes two (2) members of the minimum l
shift crew necessary for cafe shutdown and any personnel required
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for other essential f unctions during a fire emergency-1 4.
In the event of illness or unexpected absence, up to two (2) hours is allowed to restore the ahif t crew or fire brigade to the minimum complement.
i Amendment No. K, 66, J6. 111 247 L
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Amendment No.
H, 111 247a a
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6.3 PLANT STAFF QUALIFICATIONS 6.3.1 The mininum qualifications with regard to educational background 'and l
experience for plant staff positions shown in Fig 6.2-1 shall meet or exceed the minimum qualifications specified in ANSI WlB.1-1971 for l
comparable positions except for the Radiological and Environmental Services Superintendent, who shall meet or exceed the qualifications specified in Regulatory Guide 1.8, September, 1975.
6.3.2 The Shift Technical Advisor (STA) shall meet or exceed the minimum requirements of either Option 1 (Combined SRO/STA Position) or Option 2 (Continued use of STA Position), as defined in th'e Commission Policy Statement on Engineering Expertise on Shift, published in ihe October 28, 1985 Federal Register (50 FR 43621).
When invoking Option 1, the STA role may be filled by the Shift Supervisor or Assistant Shift Supervisor. (1) j 6.3.3 Any deviations will be justified to the KRC prior to an individual's i
j filling of one of these positions.
l NOTE:
(1) The 13 individuals who hold SRO licenses, and have completed I
the FitzPatrick Advanc'ed Technical Training Program prior to the issuance of this license amendment, shall be considered l
qualified as dual-role SRO/ STAS.
l l
6.4 RETRAINING AND REPLACEMENT TRAINING A training program shall be maintained under the direction of the Training Coordinator to assure overali proficiency of the plant staff organization.
It shall consist of both retraining and replacement training and shall meet or exceed the minimum requirements of Section 5.5 of ANSI N18.1-1971.
The retraining program shall not exceed periods two years in length with a curriculum designed to meet or exceed the requalification requirements of 10 CFR 55, Appendix A.
In addition fire brigade j
training shall meet or exceed the requirements of NFPA 21-1975, l
except for fire brigade training sessions which shall be held at least quarterly. The effective date for implementation of fire brigade training is March 17, 1978.
6.5 REVIEW Ah0 AUDIT Two reparate review groups for plant operations have been 3
l constituted. One of these, the Plant Operating Review Committee (PORC), is an onsite review group. The other is an independent
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review and audit group, the offsite Safety Review Committee (SRC).
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Amendment No. d, X, F2, 94, 111 248 t__._____.____.
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Table 6.2-1 POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT l
MINIMUM SHIFT MANNING REQUIREMENTS l
Refuel & Cold Shutdown Start-up, Shutdown (fuel in reactor) or Run SRO 1 on site 2 (1 in C.R.)
STA None 1 on site
- R0 1 in C.R.
2 (1 in C.R.)**
1 Non-Licensed Operator 1 on site 2 on site Individual Qualified in Radiation 1 on site 1 on site Protection Procedures i
Note:
- 1 The STA position may be combined with one of the SRO positions and fulfilled by any individual meeting the
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dual-role SR0/STA qualification in accordance with Section 6.3.2.
During startup or planned shutdown; both in Control Room. l SR0
- Licensed Senior Operator STA
- Shift Technical Advisor (C.(R.
- Licensed Reactor Operator R0
- Control Room 1
Amendment No. til 260a I
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