ML17158A043
| ML17158A043 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 12/10/1993 |
| From: | Larry Nicholson Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17158A044 | List: |
| References | |
| NUDOCS 9312170125 | |
| Download: ML17158A043 (5) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 PENNSYLVANIA POWER
& LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.
DOCKET NO. 50-387 SUS UEHANNA STEAM ELECTRIC STATION UNIT 1
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
131 License No.
NPF-14 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A. The application for the amendment filed by the Pennsylvania Power Light Company, dated July 21,
- 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission'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 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 set forth in 10 CFR Chapter I; 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.
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.
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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.
131 and the Environmental Protection Plan con-tained in Appendix B, are hereby incorporated in the license.
PPhL shall operate the facility in accordance with the Technical Specifica-tions and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Larry E. Nicholson, Acting Director Project Directorate I-2
'ivision of Reactor Projects I/II Office of Nuclear Reactor Regulation Date of Issuance:
December 10, 1993
ATTACHMENT TO LICENSE AMENDMENT NO. 131 FACILITY OPERATING LICENSE NO. NPF-14 DOCKET NO. 50-387 Replace the following pages of the Appendix A Technical Specifications with enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
REMOVE 3/4 4-If 3/4 4-Ig INSERT 3/4 4-lf 3/4 4-Ig
REACTOR COOLANT SYSTEM SURVEILLANCEREQUIREMENTS Continued 4.4.1.1.2.4 The pump discharge valve and bypass valve in both loops shall be demonstrated OPERABLE by cycling each valve through at least one complete cycle of full travel during each startup"" prior to THERMAL POWER exceeding 25% of RATED THERMALPOWER.
4.4.1.1.2.5 The pump MG set scoop tube electrical and mechanical stop shall be demonstrated OPERABLE with overspeed setpoints less than or equal to 102.5% and 105%, respectively, of rated core flow, at least once per 18
'onths.
4.4.1,1.2.6 During single recirculation loop operation, all jet pumps, including those in the inoperable loop, 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 no two of the following conditions occur:¹¹¹ a.
The indicated recirculation loop flow in the operating loop differs by more than 10% from the established single recirculation pump speed-loop flow characteristics.
b.
The indicated total core flow differs by more than 10% from the established total core flow value from single recirculation loop flow measurements.
c.
The indicated diffuser-to-lower plenum differential pressure of any individual jet pump differs from established single recirculation loop patterns by more than 10%.
4.4.1.1.2.7 The SURVEILLANCEREQUIREMENTS associated with the specifications referenced in 3.4.1,1.2a shall be followed.
See Special Test Exception 3.10.4.
If not performed within the previous 31 days.
Initial value.
Final value to be determined based on startup testing.
Any required change to this value shall be submitted to the Commission within 90 days of test completion, See specification 3.4.1.1.1 for two loop operation requirements.
¹¹ This requirement does not apply when the loop not in operation is isolated from the reactor pressure vessel.
¹¹¹ At least once per 18 months (555 days) data shall be recorded for the parameters listed to provide a basis for SUSQUEHANNA - UNIT 1 3/4 4-1f Amendment No. 9g, 131
REACTOR COOLANT SYSTEM SURVEILLANCEREQUIREIVIENTS Continued establishing the specified relationships.
Comparisons of the actual'data in accordance with the criteria listed shall commence upon the performance of required surveillances.
The LPRM upscale alarms are not required to be OPERABLE to meet this specification in OPERATIONAL CONDITION 2.
SUSQUEMANNA - UNIT 1 3/4 4-10 Amendment No.
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131