ML17054A678
| ML17054A678 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 04/18/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Niagara Mohawk Power Corp |
| Shared Package | |
| ML17054A679 | List: |
| References | |
| DPR-63-A-057 NUDOCS 8405150479 | |
| Download: ML17054A678 (14) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION, UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
57 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 November 4, 1983 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 hy 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:
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P (2) Technical S eci ficati ons The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 57, 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.
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 18, 1984 FOR THE NUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch P2 Division of Licensing
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ATTACHMENT TO LICENSE AMENDMENT NO. 57 FACILITY OPERATII'IG LICENSE NO.
DPR-63 DOCKET NO. 50-220 Revise the Appendix A Technical Specifications by removing and inserting the following pages:
Existing
~Pa e
92-115 258 Revised
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92-115 258 The revised areas are indicated by marginal lines.
Those pages left intentionally blank do not contain marginal markings.
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.2.6 INSERVICE INSPECTION AND TESTING 4.2.6 INSERVICE INSPECTION AND TESTING
~nlicability:
Applies to components which are part of the reactor coolant pressure boundary and their supports and other safety-related pressure
- vessels, piping,
- pumps, and valves.
JAA1i bill Applies to the periodic inspection and testing of components which are part of the reactor coolant pressure boundary and their supports and other safety-related pressure
- vessels, piping,
- pumps, and valves.
Ob jec tive:
To assure the integrity of the reactor coolant pressure boundary and the operational readiness of safety-related pressure
- vessels, p i p ing,
- pumps, and va 1 ves.
Objective:
To verify the integrity of the reactor coolant pressure boundary and the operational readiness of safety-related pressure
- vessels, piping,
- pumps, and valves.
deci fication:
a.
Inserv ice Ins~ect ion 1.
To be considered
- operable, equality Group A, B and C components shall satisfy the requirements contained in Section XI of the ASME Boiler and Pressure Vessel Code and appli-cable Addenda for continued service of ASME Code Class 1,
2 and 3 components, respectively, except where relief has been granted by the Commission pursuyn to
- 10CFR50, Section 50.55a(g)(6)(i).<
1 Specification:
a.
Inservice Ins ection 1.
Inservice inspection of guality Group A, B and C components shall be performed in accordance with the requirements for ASME Code Class 1,
2 and 3 components, re-spectively, contained in Secti+
XI of the ASME Boi ler and Pres-sure Vessel Code and applicable Addenda as required by 10CFR50, Section 50.55a(g),
except where relief has been granted by-the Commission pursuant to 10 CFR Part 50 Section 50.55a(g)(6)(i).(
92 Amendment Ho.
e M
LiHITINN CONDITION FOR OPERATION SURVEILLANCE REOUIRENENT 2.
An augmented inservice inspection program shall be performed in accordance with the schedules contained in HUREG 0313 Revision 1.
The augmented inservice inspection program shall be performed on service sensitive components.
The following systems contain service sensitive components:
core spray, shutdown
- cooling, emergency condensers, liquid poison, reactor head spray and control rod drive return.
b.
t ~iT 1.
To be considered
- operable, guality Group A,
B and C pumps and valves shall satisfy the requirements contained in Section XI of the ASIDE Boiler and Pressure Vessel Code and applicable Addenda for continued service of ASIDE Code Class 1,
2 and 3 components, respect ively, except where rel ief has been granted by the Commissiog pursuant to 10CFR50, Section 50.55a(g)(6)(i).I2>
b.
Inservice T~estin l.
Inservice testing of guality Group A, B and C pumps and valves shall be per-formed in accordance with the require-ments for ASNE Code Class 1,
2 and 3
components contained in Section XI of of the ASHE Boiler and Pressure Vessel Code and applicable Addenda as re-quired by 10CFR50, Section 50.55a(g),
except where relief has been granted by the Commission pursuant to 10 CfR Part 50 Section 50.55a(g)(6)(i)..(>>
Amendment Ho.
57 93
0
BASES FOR 3.2.6 AND 4.2.6 INSERVICE INSPECTION AND TESTING The inservice inspection and testing program for the Nine Mile Point Unit 1 plant conforms to the requirements of 10 CFR 50, Section 50.55a(g).
Where practical, the inspection of components, pumps and valves classified into NRC I)uality Groups A,
8 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 a deviation from that requirement is submitted to the Commission in accordance with 10 CFR 50, Section 50.55a(g)(6)(i).
Deviations which are needed from the procedures prescribed in Section XI of the ASME Code and applicable Addenda will be reported to the Commission prior to the beginning of each 10-year inspection period if they are known to be required at that time.
Deviations which are identified during the course of inspection will be reported quarterly throughout the inspection period.
I The augmented inservice inspection program for the Nine Mile Point Unit 1 plant conforms to the schedules contained in NUREG 0313 Revision 1.
It is performed in order to detect and survey intergranular stress corrosion cracking of ASME Code Class 1,
2 and 3 pressure boundary piping.
Inspections shall be performed by individuals qualified to (1) the ASME Boiler and Pressure Vessel
- Code,Section XI, as specified to the
- NRC, and (2) Ultrasonic Testing Operator Training for Intergranular Stress Corrosion Cracking developed by the EPRI Non-Destructive Examination Center,- as specified to the NRC.
References (1)
Letter from the Nuclear Regulatory Commission (D. B. Vassallo) to Niagara Mohawk Power Corporation
.(G.
K. Rhode),
dated September 19, 1983.
(2)
Letter from Niagara Mohawk Power Corporation (D. 'P. Disc) to the Nuclear Regulatory Commission (T. A. Ippolito), dated August 7,
1981.
Amendment No'.
57 94
6.10 b.
Safety Class 1 Inservice Inspection, Specification 4.2.6 (Three months) c.
Safety Class 2 Inservice Inspections, Specification 4.2.6 (Three months) d.
Safety Class 3 Inservice Inspections; Specification 4.2.6 (Three months) e.
Primary Containment Leakage Testing, Specification 3.3.3 (Three months) f.
Secondary Containm nt Leakage Testing, Specification 3.4.1 (Three months) g.
Sealed Source Leakage In Excess Of Limits, Specification 3.6.5.2 (Three months)
Record Retention 6.10.1 The following records shall be retained for at least five years:
a.
Records and logs of facility operation covering time interval at each power level.
b.
Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.
c.
REPORTABLE OCCURRENCE Reports.
Amendment No.
57 258
0