ML20071P340
| ML20071P340 | |
| Person / Time | |
|---|---|
| Site: | Mcguire |
| Issue date: | 05/27/1983 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20071P344 | List: |
| References | |
| NUDOCS 8306070431 | |
| Download: ML20071P340 (4) | |
Text
l DUKE P0tlER COMPANY DOCKET NO. 50-370 MCGUIRE NUCLEAR STATION, UNIT 2 FACILITY OPERATING LICENSE AMENDMENT NO. 2 LICENSE NO. NPF-17 1.
The Nuclear Regulatory Corraission (the Comission) has found that:
A.
The application, as amended, for license filed by the Duke Power Company (the licensee) complies with the standards and requirements of the
. Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the application,.as anended, the provisions of the Act, and the regulations of the Corinission; C.
There is reasonable assurance:
(1) that the activities cuthorized by this operating license 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 set forth in 10 CFR Chapter I; D.
The issuance of this license amendr.ent will not be ininical to the comon defense and security or to the health and safety of the public; E.
The issuance of this license amendment is in accordance with 10 CFR Part 51, of the Comission's regulations and all applicable requirenents have been satisfied; 2.
Facility Operating License NPF-17 is anended as follows:
A.
Paragraph 2.C.(1) is hereby modified to read as follows:
(1) Maxinun Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3411 megawatts thernal (100". power) in accordance with the conditions specified herein and in Attachment I to this license. The preoperational tests, startup tests and other itens identified in Attachment I to this license shall be completed as specified. Attachnent 1 is hereby incorporated into this ifcense.
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. B.
Paragraph 2.C.(6) is hereby nodified to read as follows; (6) Environnental Qualification (Section 7.8 of SER, 55LR 74, 75, #0, F7)
The licensee shall environnentally qualify all electrical equipment within the scope of 10 CFR 50.49 in accordance with the implementation requirements of 10 CFR 50.49 (g).
C.
Paragraph 2.C.(10)e. 1) is hereby modified to read as follows:
1)
Prior to startup following the first refueling outage, the licensee shall:
- a. Install two additional igniter units in the containment lower compartment and four additional igniter units in the containment upper compartment in locations acceptable to the NRC staff.
- b. Provide a means acceptable to the HRC staff of verifying the operational status of the hydrogen control systen in the nain control room.
- c. Provide the capability to actuate the Hydrogen Hitiga-tion System from the control roon.
D.
Paragraph 2.C.(12) is hereby added to read as follows:
(12) Reactor Trio Breakers (Section 7.2 of SSER #7)
- a. By June 3,1983, the licensee shall provide a progran plan for conducting a life-test of the undervoltage trip attachment. The life-test progran is to be reviewed by the staff before implementation.
- b. The licensee shall nodify the design of the automatic shunt trip of the main reactor trip breakers to install an independent fusing schene. This nodification shall be implenented on a schedule consistent with the sche-dule requirements of the NRC Salem Task Force generic program.
- c. The licensee shall implement the reactor trip breaker and reactor trip bypass breaker testing and reporting as described in Table 1.
- d. Within 60 days from issuance of this anendment, the licensee shall provice the ungraded nnet trin roviou procedures for NRC staff review.
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. 3.
This license amendnent is effective as of its date of issuance.
FOR Ti1E NUCLEAR REGULATORY COMt1ISSION f
h 1-Darrell G. Eisenhut, Director Division of Licensing Date of Issuance:
May 27, 1983
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TABLE 1.
PERIODIC SURVEILLANCE / MAINTENANCE OF REACTOR TRIP BREAKERS AND REACTOR TRIP BYPASS BREAKERS EVERY 6 MONTHS PRIOR TO EACH STARTUP MONTHLY SURVEILLANCE SURVEILLANCE / MAINTENANCE (if not completed within past 7 days)
(each breaker every 31 days)
(Reactor Trip and Reactor (Reactor Trip Breakers)
(Reactor Trip Breakers)
Trip Bypass Breakers) 1.
functional test of UV trip device
- 1. a. functional test of..UV 1.
response time testing of UV/
)
independently trip device (independent) breaker on UV signal from RPS.
(visicorder shall be used
- b. response time testing of and data trended)**
UV/breakor on UV signal from RPS.
(event recorders may be used) 2.
functional test of Shunt trip device 2. functional test of Shunt trip 2.
trip shaft force measurements **
I independently device independently i
3.
functional test of manual reactor 3.
UV output force measurement **
1 trip from the control room 4.
functional test of Shunt trip i
device independently 1
5.
servicing / lubrication / adjust-
{
ments in accordance with li :
5 censee's maintenance procedures I.
6.
check the dimensional tolerances
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of pre-and post-travel of the trip tab **
7.
Insget lubricant and cleanliness of. Roller-Beari ng ** -
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- 0n fai1ure of any reactor trip breaker or reactor trip bypass breaker, either in service or during testing (on either undervoltage or shunt coils), preserve evidence of failure and notify the Commission pursuant to Technical Specification 6.9.1.10.
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- To be performed before and after preventive maintenance.
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