ML20249C640
| ML20249C640 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 06/24/1998 |
| From: | Thomas C NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20249C641 | List: |
| References | |
| NUDOCS 9806300472 | |
| Download: ML20249C640 (5) | |
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UNITED STATES g
j NUCLEAR REGULATORY COMMISSION p
4 WASHINGTON, D.C. 200eN201 NORTH ATLANTIC ENERGY SERVICE CORPORATION. ET AL?
DOCKET NO. 50-443 SEABROOK STATION. UNIT MO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.58 License No. NPF-86 1.
The Nuclear Regulatory Commission (the Commusion) has found that:
A.
The application for amendment filed by the North Atlantic Energy Service Corporation, et al. (the licensee), dated March 2,1998, as supplemented by letter dated April 21, 1998, complies with the standards and requirements of the Atomic Energy Act of l
1954, as c. mended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;
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B.
The facility will operate in conformity with the application, the provisions of the Act, l
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; l-l-
D.
The issuance of this amendmeat will not be inimical to the common defense and l
security or to the health and safety of the oublic; and -
l E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the L
Commission's regulations and all applicable requirements have been satisfied.
- North Atlantic Energy Service Corporation (NAESCO) is authorized to act as agent for the:
North Atlantic Energy Corporation, Canal Electric Company, The Connecticut Light and Power Company, Great Bay Power Corporation, Hudson Light & Power Department, Massachusetts j
Municipal Wholesale Electric Company, Montaup Electric Company, New England Power Company, New Hampshire Electric Cooperative, Inc., Taunton Municipal Light Plant, The l.
United illuminating Company, and Vermont Electric Generation and Transmission Cooperative, Inc., and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility, i
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PDR ADOCK 05000443
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2-2.
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. NPF-86 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 58, and the Environmental Protection Plan contained in Appendix B are incorporated into Facility License No. NPF-86. NAESCO shall operate the
. facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION h
Cecil O. Thomas, Director Project Directorate 1-3 Division of Reactor Projects-t/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specification-Date ofissuance: June 24, 1998 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 58 FACILITY OPERATING LICENSE NO. NPF-86 DOCKET NO. 50-443
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i Replace the following page of the Appendix A, Technical Specifications, with the attached page as indicated. The revised page is identified by amendment number and contains vertical lines indicating the area of change. An overieaf page has been provided.*
Remove jo&Rd j
3/4 5-5 3/4 5 5 l
3/4 5-6*
3/4 5-6*
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EMERGENCY CORE C001ING SYSTEMS ECCS SUBSYSTEMS - T GREATER THAN OR E00AL TO 350 F x
' SURVEILLANCE RE001REMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying that the following valves are in a.
the indicated positions with power to the valve operators reroved:
Valve Number Valve Function h1ve Position SI-V-3 Accumulator Isolation Open*
SI-V-17 Accumulator. Isolation Open*- -
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SI-V-32' Accumulator Isolation Open*
SI-V-47 Accumulator Isolation Open*
SI-V-114 SI Pump to Cold-Leg Isolation Open RH-V-14 RHR Pump to Cold-Leg Isolation Open RH-V-26 RHR Pump to Cold-Leg Isolation Open A
RH-V-32 RHR to Hot-Leg Isolation Closed RH-V-70 RHR to Hot-Leg Isolation Closed SI-V-77 SI to Hot-Leg Isolation Closed SI-V-102 SI to Hot-Leg Isolation Closed b.
At least once per 31 days by:
1)
Verifying that the ECCS piping is full of water by venting the ECCS pump casings (excluding the operating centrifugal charging pump) and accessible discharge piping high points and i
2)
Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position, By a visual inspection which verifies that no loose debris (rags, trash, c.
clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during l
LOCA conditions. This visual inspection shall be performed:
1)
For all accessible areas of the containment prior to establishing primary CONTAINMENT INTEGRITY, and I
2)
At least once daily of the areas affected within containment by containment entry and during the final entry when primary CONTAINMENT INTEGRITY is established.
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- Pressurizer pressure above 1000 psig.
-SEABROOK - UNIT 1 3/4 5 5 Amendment No. 9058 m.
EMERGENCY CORE COOLING SYSTEMS Ects SUBSYSTEMS - T CREATER THAN OR EDUAL TO 350'F SURVEILLANCE R DUIREMENTS 4.5.2 (Continued) d.
At least once per 18 months by:
1)
Verifying automatic interlock action of the RHR system from the Reactor Coolant $ stem to ensure that with a simu lated or actual Reactor Coolant stem pressure signal greater than or soual to 365 psig, the inter 1 ks prevent the valves from being opened.
2)
A visual inspection of the containment sump and v'erifying that the structural distre(trash racks, screens, ion. ) y debr subsystem suction inlets are not restricted b sump components etc.
show no evidence of ss or abnormal corros e.
At least once per 18 months, during shutdown, by:
1)
Verifying that each automatic valve in the flow path actuates to its correct position on (Safety Injection actuation and Automatic Switchover to Containment Sump) test signals, and 2)
Verifying that each of the following pumps start automatically upon receipt of a Safety Injection actuation test signal:
a)
Centrifugal charging pump, b)
Safety Injection pump, and c)
RHR pump.
differen>3ial pressure on recirculation flow when tested pursuant toBy verif ine that each of the following pumps develops the indicated f,,
Specification 4.0.5:
1)
Centrifugal charging pump, k 2480 psid;,
2)
Safety Injection pump, k 1445 psid; and 3)
RHR pump, k 171 psid.
.j SEABROOK - UNIT 1 3/4 5-5 Amendment No. 33 GI23tw
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