ML17146A973
| ML17146A973 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 09/23/1987 |
| From: | Boger B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17146A974 | List: |
| References | |
| NUDOCS 8709300334 | |
| Download: ML17146A973 (9) | |
Text
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 PENNSYLVANIA POWER 5 LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-387 SUS UEHANNA STEAM ELECTRIC STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 7l License No. NPF-14 1.
The Nuclear Regulatory Comission (the Commission or the NRC) having found that:
A.
The application for the amendment filed by the Pennsylvania Power Il Light Company, dated September 14, 1987, 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; B.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the ComIission; C.
There is reasonable assurance:
(i) that the activities authorized by this amendment can be conducted without endanger'ing 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 amendment will not be. inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-14 is hereby amended to read as follows:
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 7l and the Environmental Protection Plan con-tained in Appendix 8, are hereby incorporated in the license.
PPKL shall operate the facility in accordance with the Technical Specifica-tions and the Environmental Protection Plan.
8709300334 870923~
3.
This license amendment became effective September 14, 1987.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
"september 23, 1987
/s/
Bruce A. Boger, Assistant Director for Region I Reactors Division of Reactor Projects I/II Office of Nuclear Reactor Regulation i'
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This license amendment became effective September 14, 1987.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
Septeaber 23, 1987, Bruce A. Boger, Assistant Director for Region I Reactors Division of Reactor Pro)ects I/II Office of Nuclear Reactor Regulation
1
ATTACHMENT TO LICENSE AMENDMENT NO. 71 FACILITY OPERATING LICENSE NO. NPF-14 DOCKET NO. 50-387 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised page is identified by Amendment number and contains vertical lines indicating the area of change.
The overleaf page is provided to maintain document completeness.*
REMOVE 3/4 3-51 3/4 3-52*
INSERT 3/4 3-51 3/4 3-52*
INSTRUMENTATION 3/4.3.6 CONTROL ROD BLOCK INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.6.
The control rod block instrumentation channels shown in Table 3.3.6-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.6-2.
APPLICABILITY: As shown in Table 3.3.6-1.
ACTION:
With a control rod block instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.6-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value."
b.
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, take the ACTION required by Table 3.3.6-1.
SURVEILLANCE RE UIREMENTS 4.3.6 Each of the above required control rod block trip systems and instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.6-1.
"For the Intermediate Range Monitors the provisions of Specification 3.0.4 are not applicable for the purposes of entering Operational Condition 5 from Operational Condition 4 on September 14, 1987.
SUSQUEHANNA - UNIT 1 3/4 3-51 Amendment No. 71 Effective Date:
September 14, 1987
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O TABLE 3.3.6-1 CONTROL ROD BLOCK INSTRUHENTATION HINIHUH OPERABLE CHANNELS PER TRIP FUNCTION TRIP FUNCTION 1.
ROD BLOCK MONITOR a.
Upscale b.
Inoperative c.
Downscale 2.
APRH a.
Flow Biased Neutron Flux-Upscale b.
Inoperative c.
Downscale d.
Neutron Flux - Upscale, Startup 3.
SOURCE RANGE MONITORS a.
Detector not full in(b) 3 2
3 2
3 2
3 2%*A b.
Upsca1 e c.
Inoperative (c) d.
Downscale 4.
INTERMEDIATE RANGE HONITORS a.
Detector not full in b.
Upscale c.
Inoperati~~)
d.
Downscale 5.
Water Level-High 6.
REACTOR COOLANT SYSTEM RECIRCULATION FLOW a.
Upscal e b.
Inoperative c.
Comparator APPLICABLE OPERATIONAL CONDITIONS 1*
1*
11,2,5 1
2, 5
2, 5
2, 5
2, 5
2, 5
5**
ACTION 60 60 60 61 61 61 61 61 61 61 61 61 61 61 61 61 61 61'1 62 62 62 62