ML20029E072
| ML20029E072 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 05/09/1994 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | North Atlantic Energy Service Corp |
| Shared Package | |
| ML20029E073 | List: |
| References | |
| NPF-86-A-031 NUDOCS 9405160218 | |
| Download: ML20029E072 (4) | |
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UNITED STATES SQgg'}e NUCLEAR REGULATORY COMMISSION Q,y WASHINGTON, D.C. 2055tH)001
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NORTH ATLANTIC ENERGY SERVICE CORPORATION. ET AL*
DOCKET NO. 50-443 SEABROOK STATION. UNIT NO. 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 31 License No. NPF-86 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by North Atlantic Energy Service Corporation, et al. (the licensee), dated September 13, 1993, 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; 8.
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.
Tho 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.
9405160218 940509 PDR ADOCK 05000443-P PDR
i 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 Sorcifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 31, and the Environmental Protection Plan contained in Appendix B are incorporated into Facility License No.
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, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION John F. Stolz, Director Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 9, 1994
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i alTACHMENT T0 tICENSE AMENDMENT NO. 31
[ AGILITY OPERATING LICENSE N0. NPF-86 DOCKET N0. 50-443 Replace the following page of Appendix A, Technical Specifications, with the attached page as indicated. The revised page is identified by amendment number and contains vertical lines indicating the areas of change. The-overleaf pages has been provided.
Remove Insert 2-3*
2-3*
2-4 2-4
1&EETV LIMITS AN9 LIMITING SAFETY SYSTEM SETTINGS 4
2.2 LIMITING SAFETY SYSTEM SETTINGS REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS 2.2.1 The Reactor Trip System Instrumentation and Interlock Setpoints shall be set consistent with the Trip Setpoint values shown in Table 2.2-1.
APPLICABILITY: As shown for each channel-in Table 3.3-1.
ACTION:
a.
With a Reactor Trip System Instrumentation or Interlock Setpoint less conservative than the value shown in the Trip Setpoint column but more conservative than the value shown in the Allowable Value column of Table 2.2-1, adjust the Setpoint consistent with the Trip Setpoint value.
b.
With the Reactor Trip System Instrumentation or Interlock Setpoint less conservative than the value shown in the Allowable Value column of Table 2.2-1, either:
1.
Adjust the Setpoint consistent with the Trip Setpoint value of Table 2.2-1 and determine within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that Equation 2.2-1 was satisfied for the affected channel, or 2.
Declare the channel inoperable and apply the applicable ACTION statement requirement of Specification 3.3.1 until the channel is restored to OPERABLE status with its Setpoint adjusted consistent with the Trip Setpoint value.
Equation 2.2-1 Z + R + S s TA Where:
Z-The value from Column Z of Table 2.2-1 for the affected
- channel, R=
The "as measured" value (in percent span) of rack error for the affected channel, S-Either the "as measured" value (in percent span) of the sensor error, or the value from Column S (Sensor Error) of Table 2.2-1 for the affected channel, and TA - The value from Column TA (Total Allowance) of Table 2.2-1 for the affected channel.
SEABROOK UNIT 1 2-3
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1
M TABLE 2.2-1 g
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS h
SENSOR e
TOTAL ERROR g
FUNCTIONAL UNIT ALLOWANCE (TA)
Z (S)
TRIP SETPOINT ALLOWABLE VALUE 1.
Manual Reactor Trip N.A.
N.A.
N.A.
N.A.
N.A.
2.
Power Range, Neutron Flux a.
High Setpoint 7.5 4.56 1.42 s109% of RTP*
slll.1% of RTP*
b.
Low Setpoint 8.3 4.56 1.42 s25% of RTP*
$27.1% of RTP*
3.
Power Range, Neutron Flux, 1.6 0.5 0
s5% of RTP* with 56.3% of RTP* with High Positive Rate a time constant a time constant 22 seconds 22 seconds 7
4.
Power Range, Neutron Flux, 1.6 0.5 0
s5% of RTP* with s6.3% of RTP* with High Negative Rate a time constant a time constant 22 seconds 22 seconds 5.
Intermediate Range, 17.0 8.41 0
525% of RTP*
s31.1% of RTP*
Neutron Flux 5
5 6.
Source Range, Neutron Flux 17.0 10.01 0
$10 cps 51.6 x 10 cps 7.
Overtemperature AT 6.5 3.5 1.7** See Note 1 See Note 2
+0.5**
8.
Overpower AT 4.9 2.2 1.7 See Note 3 See Note 4 9.
Pressurizer Pressure - Low 3.12 0.86 0.99 21945 psig 21,931 psig 10.
Pressurizer Pressure - High 3.12 1.00 0.99 s2385 psig 52,398 psig 5
- e - F A!!D lui hMAl POWER
- I r.c u s. sus error for I is 1.7 and the sensor error for Pressurizer Pressure is 0.5.
"As measured" sensor errors may be uIe*d in lieu of either or both of these values, which then must be summed to determine the overtemperature AT total channel value for S.
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