ML20247F716
| ML20247F716 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 09/07/1989 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247F721 | List: |
| References | |
| NUDOCS 8909180253 | |
| Download: ML20247F716 (9) | |
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. NUCLEAR REGULATORY COMMISSION E
E WASHINGTON, D. C. 20555 i::
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POWER AUTHORITY OF THE STATE OF NEW YORK l
DOCKET NO. 50-333 -
JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE i
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Amendment No. '137 1
License No. DPR-59
- 1..
The Nuclear Pegulatory Comission (the Comission) has'found that:
.A.
The application for amendment by Power Authority of the State of New York (the licensee) dated May 19, 1989, complies with the standards ano 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; 4
D.
The facility will operate in conformity with the application, I
the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable asu rance (i) that the activities authorized by this amendment can he 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 amenduent 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 accorcance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements l
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.C.(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.137 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 to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Y N T-W Robert A. Capra, Director Project Directorate 1-1 Division of Reactor Projects - I/II
' Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuence:
September 7, 1989 i
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J ATTACHMENT ~TO LICENSE AMENDMENT NO. 137
-it FACILITY OPERATING LICENSE NO. DPR-59 I
DOCKET NO.'50-333 I
ReviseAppendixAasfollows: -
Remove Pages.
Insert Pages iii.
111 vii
. vii 247-'
247 247a 247a 248 248 y-
'259 259-260 260 F
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4xgypp 2AELE OF RDFTENTS (cont'd)
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.Page J
- D.
Emergency Service Water. System 240
- E... Intake Deicing Heaters 242 3.12 Fire Protection Systems 244a 5.0 Design features 245 5.1 Site 245 L
5.2 Reactor 245 1:
5.3 Reactor Pressure, Vessel 245 5.4 Containment 245 5.5 ruel Storage 245 5.6 Seismic Design 246 6.0 Administrative controls 247 l'
6.1 Responsibility 247
.6.2, Organization 247' 6.2.1 Facility Management and Technical Support 247 6.2.2 Plant Staff' 247a 6.3-
' Plant Staff Qualifications 248 6.4 Retraining and Replacement Training 248 6.5 Review and Audit 248
- 6. 5.1 - Plant Operating Review Committee (PORC) 248a L
6.5.2 Safety Review Committee (SRC) 250 6.6 Reportable Event Action 253 6.7 Safety Limit Violation 253 6.8 Procedures 253 l
6.9 Reporting Requirements 254a 6.10 Record Retention 2549 6.11 Radiation Protection Program 255 6.12 Industrial Security Program 258 6 13 Emergency Plan 258 6.14 Fire Protection Program 258 6.15 Environmental Qualification 258a Amendment No. /, g, )(, K, g,,93', }ID 111 AMENDMENT NO. 137 L
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LIST OF FIGURES Floure Title Eggg.
3.1-1 Manual Flow Control 47a 3.1-2 Operating Limit MCPR versus 47b 4.1-1 Graphic Aid in the Selection of an Adequate Interval Between Tests 48
. 4.2-1 Test Interval vs. Probability of System Unavailability 87 3.4-1 Sodium Pentaborate Solution of System Volume-Concentration Requirements 110 3.4-2 Saturation Temperature of Sodium Pentaborate Solution 111 3.5-1 Thermal Power and Core Flow Limits of Specifications 3.5.J.1, 3.5.J.2 and 3.5.J.3 134 3.5-6 (Deleted) 1356 3.5-7 (Deleted) 135e 3.5-8 (Deleted) 135f 3.5-9 (Deleted) 135g 3.5-10 (Deleted) 135h 3.5-11 MAPLHGR Versus Planar Average Exposure Reload 6 & 7, BP8DRB299, QUAD +
1351
- 3.5-12 MAPLHGR Versus Planar Average Exposure Reload 7 BD319A 135) 3.5.13 MAPLHGR Versus Planar Average Exposure Reload 8, BD336A 135k 3.5.14 MAPLHGR Versus Planar Average Exposure Reload 8, BD339A 1351 3.6-1 Reactor Vessel Thermal Pressurization Limitations 163 4.6-1 Chloride Stress Corrosion Test Results at 500*F 164 6.1-1 (Deleted) 259 6.2-1 (Deleted) 260 Amendment No. /, g, $df, M, W, K, % Sdf, M, g, g vil AMENDMENT WO.
137
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6.0 ADMINISTRATIVE CONTROLS Administrative Controls are the means by which piant operations, 2 subject to management rntrol. Measures specified in thi.s secGen provide for the,rmgnmen: et responsibilities. plant organization, statfing qualifications and related requirements.
review and audit mechanisms, procedural controls and reporting requirements. Each of these measures are necessary to ensure safe and efficient faciliry eperation.
o.1 RESPONSIBILITY 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.
It2 Organization 62.1 Facility Manacement and Technical Support Onsite and offsite organizations shall be established for plant operation and corporate management, respectively. The onsite and offsite organizations sh,il include the positions for activities that affect the safety of the nuclear power plant.
1.
Lines of authority, responsibility, and communication sr all be established and defined for the highes'. management levels through intermediate leve's to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organiza1 ion charts, functional descriptions of departmental responsibilities and relationships, ano job descriptions for key personnel positions, or in equivalent forms of documentation.
These requirements shall be documented in the Updated FSAR.
2.
Ti:a Resident Manager shall be responsible for overall plant operatica, and shall hase control ever those onsite activities that are necessary for safe operation and maintenance of the plant.
3.
The Executive Vice President - Nuclear Generation shall take any measures needed to eraure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
Amendment No.pf p5, N,Jd 247 AMENDMENT NO.
137
4.
The 2dividuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
'i22 P! ant Staff The plant staff organization shall be as fodows:
1.
Each shift crew shall be composed of at least the minimum shift crew canposition shown in Table 6.21; 2.
An SRO or an SRO with a license limited to fuel handling shall directly supersise I
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 shift crew necessary for safe shutdown and any personnel required for other essential functions during a fire emergency; 4.
In the event ofillness or unexpected absence, up to two (2) hours is allowed to restcue the shift crew or fire brigade to the minimum compliment; 5.
The Operatier.s Superintendent, Assistant Operations Superintendent, Shift Supervisor and Assistant Shift Supervisor shall hold a SRO license and the Senior Nuclear Operator and the Nuclear Control Operator shall hold a RO licen e.
Amendment No. 4(, /
AMENDMENT NO.
137
' 6.3 Pl. ANT STAFF QUALIFICATIONS 6.3.1 The minimum qualifications with regard to educational background and experience for l
plant staff positions shown in FSAR Figure 13.2-7 shall meet or exceed the minimum qualifications specified in ANSI N18.1-1971 for 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.
1 6.3.2 The Shift Technical Advisor (STA) shall meet or exceed the minimum requirements of
.I either Option 1 (Combined SRO/STA Position) or Option 2 (Continued use of STA Position), as denned in the Commission Policy Statement on Engineering Expertise on Shift, published in the 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.
i (1) 63.3 Any deviations will bejustified to the NRC prior to an individual's filling of one of these positions.
NOTE:
(1)
The 13 individuals who hold SRO licenses, and have completed the FitzPatrick Advanced Technical Training Program prior to the issuance of License Amendment 111, shall be considered qualified as dual-role SRO/ STAS.
6.4 RETRAINING AND REPLACEMENTTRAINING A training program shall be maintained under the direction of the Training Superintendent to assure overall 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 cf ID CFR 55, Appendix A.
In addition fire brigade training shall meet or exceed the requirements of NFPA 21-1975, 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 AND AUDIT Two separate review groups for plant operations have been constituted. One of these, the Plant Operating Review Committee (PORC),is an onsite eview group. The other is an independent review and audit group, The offsite Safety Review Committee (SRC).
Amendment No.M/)(,J#f 248 AMENDMENT NO.
137
l THIS PAGE INTENTIONALLY LETT 3 LANK The next page is 260a Amendment No.f6, M, M, M 259-260 AMENDMENT NO.
137
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