ML20094P974
| ML20094P974 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  (NPF-86-A-044, NPF-86-A-44) |
| Issue date: | 11/28/1995 |
| From: | Mckee P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20094P975 | List: |
| References | |
| NUDOCS 9511300282 | |
| Download: ML20094P974 (7) | |
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WASHINGTON, D.C. 30806 0001 NUCLEAR REGULATORY COMMISSION 1
1 NORTH ATLANTIC ENERGY SERVICE CORPORATION. ET AL*
f DOCKET NO.'50-443 4
I SEABROOK STATION. UNIT NO. I AMENDMENT TO FACILITY OPERATING LICENSE 1
Amendment No. 44 License No. NPF-86 i
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The Nuclear Regulatory Commission (the Commission) has found that:
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'A.
The application for amendment by North Atlantic Energy Service Corporation, et al. (the licensee), dated July 24, 1995, and supplemented by letter dated October 30, 1995, complies with the i
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 Connission's regulations; D.
The issuance of this amendment will not be inimical to the common 1
defsnse 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.
- North Atlantic Energy Service Company (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 and Power Department, Massachusetts Municipal-Wholesale Electric Company, Montaup Electric Company, New England Power Company, New Hampshire Electric Cooperative, Inc., Taunton Municipal Light Plant, and The United Illuminating Company, and has exclusive responsibility and control over the physical construction, operation, and maintenance of the facility.
i 9511300282 951130 PDR ADOCK 05000443
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, l
and paragraph 2.C.(2) of Facility Operating License No. NPF-86 is hereby amended to read as follows:
(2) Itchnical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 44, 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 the date of its issuance, and is to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY C0ftlISSION Phillip F.
cKee, Director Project Directorate I-3 Division of Reactor Projects - I/II 1
Office of Nuclear Reactor Regulation j
Attachment:
Changes to the Technical Specifications Date of Issuance: November 28, 1995 1
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I ATTACHMENT TO LICENSE AMENDMENT NO. 44 FACILITY OPERATING LICENSE NO. NPF-86 DOCKET NO. 50-441 Replace the following pages of Appendix A, Technical Specifications, with the i
attached pages as indicated. The revised pages are identified by amendment number and contain verticp1 lines indicating the areas of change. Overleaf pages have been provided l
Remove Insert 3/4 4-21 3/4 4-21 3/4 4-22*
3/4 4-22*
3/4 4-23 3/4 4-23 3/4 4-24 3/4 4-24 i
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REACTOR COOLANT SYSTEM LEAKAGE OPERATIONAL LEAKAGE I
LIMITING enunITION FOR OPERATION J
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3.4.6.2 Reactor Coolant System leakage shall be limited to:
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a.
No PRESSURE B0UNDARY LEAKAGE, I
b.
I gpa UNIDENTIFIED LEAKAGE, c.
I gpa total reactor-to-secondary leakage through all steam l
generators and 500 gallons per day through any one steam generator, j
d.
10 gpa IDENTIFIED LEAKAGE from the Reactor Coolant System, i
e.
'40 gpa CONTROLLED LEAKAGE at a Reactor Coolant System pressure of 2235 psig i 20 psig, and i
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0.5 gpa leakage per nominal inch of valve size up to a maximum of 5 j
gpa at a Reactor Coolant System pressure of 2235 i 20 psig from arg Reactor Coolant System Pressure Isolation Valve.*
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APPLICABILITY: MODES 1, 2, 3, and 4.
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ACTION:
a.
With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With any Reactor Co21 ant System leakage greater than any one of the j
above limits, excluding PRESSURE BOUNDARY LEAKAGE and leakage from Reactor Coolant System Pressure Isolation Valves, reduce the leakage o
rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT STANDBY l
within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
c.
With any Reactor Coolant System Pressure Isolation Valve leakage l
greater than the above limit, isolate the high pressure portion of j
the aff'ected system from the low pressure portion within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by j
use of at least two closed manual or deactivated automatic valves, 1
or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- Test pressures less than 2235 psig but greater than 150 psig are allowed.
l Observed leakage shall be adjusted for the actual test pressure up to 2235 psig assuming the leakage to be directly proportional to pressure dif-
.ferential to the one-half power.
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SEABROOK - UNIT 1 3/4 4-21 Amendment No. 44
4 REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM LEAKAGE OPERATIONAL LEAKAGE
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SURVEILLANCE RfeUIREMENTS
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4.4.6.2.1 Reactor Coolant System leakages shall be demonstrated to be within j
each of the above limits by:
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a.
Monitoring the containment atmosphere particulate radioactivity j
monitor at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; l
b.
Monitoring the containment drainage sump inventory and discharge at j
least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />;
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c.
Measurement of the CONTROLLED LEAKAGE to the reactor coolant pump
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seals when the Reactor Coolant System pressure is 2235 i 20 psig at least once per 31 days with the modulating valve fully open. The i
provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4; d.
Performance of a Reactor Coolant System water inventory balance within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after. achieving steady-state operation
- and at least i
once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> thereafter during steady-state operation, except' that not more than 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> shall elapse between any two successive inventory balances; and e.
Monitoring the Reactor Head Fiance Leakoff System at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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- T, being changed by less than 5'F/ hour.
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i SEABROOK - UNIT 1 3/4 4-22
l REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM LEAKAGE OPERATIONAL LEAKAGE i
SURVEILLANCF unulREMENTS I
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4.4.6.2.2 Each Reactor Coolant System Pressure Isolation Valve shall be l
demonstrated OPERABLE by verifying leakage to be within its limit:
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a.
At least once per 18 months, b.
Prior to entering MODE 2 whenever the plant has been in COLD j
SHUTDOWN for 7 days or more and if leakage testing has not been i
performed in the previous 9 months, c.
Prior to returning the valve to service following maintenance, I
repair, or replacement work on the valve, and a
d.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following valve aptuation due to automatic or manual action or flow through the valve l
e.
As outlined in the ASME Code,Section XI, paragraph IWV-3427(b).
The provisions of Specification 4.0.4 are not applicable for entry into i
MODE 3 or 4.
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- Not applicable to RHR Pumps 8A and 8B suction isolation valves.
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SEABROOK - UNIT 1 3/4 4-23 Amendment No. 44 1
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l SEABROOK - UNIT 1 3/4 4-24 Amendment No. 44 4
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