ML17056A107
| ML17056A107 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 07/07/1989 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17056A108 | List: |
| References | |
| GL-88-01, GL-88-1, NUDOCS 8907180378 | |
| Download: ML17056A107 (10) | |
Text
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UNITED STATES 1
NUCLEAR R EG ULATORY COMMISS ION WASHINGTON, O. C. 20555 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment tlo.107 License No. DPR-63 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated October 19, 1988, 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 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.C.(2) of Facility Operating License No. DPR-63 is hereby amended to read as follows:
8907180378 890707 PDR ADOCK 05000220 P
(2)
Technical S ecifications The Technical Speci ficati ons contained in Appendices A and 8, as revised through Amendment No. 107, 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
%~a.. G~~
Robert A. Capra, Director Project Directorate I-I Division of Reactor Projects, I/II
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 7, 1989
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
107 TO FACILITY OPERATING LICENSE NO. DPR-63 DOCKET NO. 50-220 Revise Appendix A as fo1'lows:
Remove Pa es 93 94 Insert Pa es 93 94
LIHITING CONDITION FOR OPERATION SURVEILLANCE REQUIREHENT 2.
The Inservice.Inspection Program for piping identified in NRC Generic Letter 88-0I shall be performed in accordance with the staff positions on schedule,
- methods, personnel and sample expansion included in this generic letter.
b.
Inservice Testin 1.
To be considered
- operable, Quality Group A, B and C pumps and valves, shall satisfy the requirements contained in Section XI of the ASHE Boiler and Pressure Vessel Code and applicable Addenda for continued service of ASHE Code Class 1,
2 and 3 components, respectively, except where relief has been granted by the Commission pursuant to 10CFR50, Section 50.55a(g)(6)(i).
c.
Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.
d.
Nothing in the ASHE Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.
b.
Inservice Testin l.
Inservice testing of Quality Group A,
B and C pumps and valves shall be performed in accordance with the requirements for ASHE Code Class I, 2 and 3 components contained in Sectidn XI of the ASHE Boiler and Pressure Vessel Code and applicable Addenda as required by 10CFR50, Section 50.55a(g),
except where relief has been granted by the Commission pursuant to 10CFR Part 50, Section 50.55a(g)(6)(i).
Amendment Ho. 107,
BASES FOR 3.2.6 AND 4.2.6 INSERVICE INSPECTION AND TESTING The inservice inspection and testing programs(1)(2) for the Nine Mile Point Unit 1 plant conform to the requirements of 10CFR50, Section 50.55a(g).
Nhere practical, the inspection of components, pumps and valves classified into NRC Quality Groups A,-B and C conforms to the requirements of ASME Code Class 1,
2 and 3
components, pumps and valves, respectively, contained in Section XI of the ASME Boiler and Pressure Vessel Code.
If a Code required inspection is impractical for the Nine Mile Point Unit 1 facility, a request for relief from that requirement is submitted to the Commission in accordance with 10CFR50, Section 50.55a(g)(6)(i).
Request for relief from the requirements of Section XI of the ASME Code and applicable Addenda will be submitted to the Commission prior to the beginning of each 10-year inspection interval if they are known to be required at the time.
Requests for relief which are identified during the course of inspection will be submitted quarterly throughout the inspection interval.
The inservice inspection program for piping conforms to the staff positions on schedules,
- methods, personnel and sample expansion contained in Generic Letter 88-01.(3)
It is performed in order to detect and survey intergranular stress corrosion cracking of BNR austenitic stainless steel piping that is four inches or larger in nominal diameter and contains reactor coolant at a temperature above 200'F during power operation.
Inspections shall be performed by individuals qualified to:
(A) the ASME Boiler and Pressure Vessel
- Code,Section XI, and (B) Ultrasonic Testing Operator Training for the Detection of Intergranular Stress Corrosion Cracking developed by the EPRI Non-Destructive Examination Center.
As an alternate, Niagara Mohawk may use other qualification programs approved by the NRC.
References Letter from the Nuclear Regulatory Commission (D. B. Vassallo) to Niagara Mohawk Power Corporation (G. K.
Rhode),
dated September 19, 1983.
Letter frqm Niagara Mohawk Power Corporation (D. P. Disc) to the Nuclear Regulatory Commission (T. A.
Ippolito), dated August 7, 1981.
Generic Letter 88-01 endorses NUREG 0313 Revision 2, "Technical Report on Material Selection and Processing Guidelines for BNR Coolant Pressure Boundary Piping," dated January 1988.
Amendment No.
- 107, 94
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