ML17146A908
| ML17146A908 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 08/17/1987 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17146A909 | List: |
| References | |
| NUDOCS 8708250132 | |
| Download: ML17146A908 (10) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 PENNSYLVANIA P014ER 8t LIGHT COMPANY ALLEGHENY ELFCTRIC COOPERATIVE, INC.
DOCKET NO. 50-387 SUS UEHANNA STEAM ELECTRIC STATION, UNIT I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 67 License No.
NPF-14 I.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for the amendment filed by the Pennsylvania Power 5 Light Company, dated April 8, 1987, 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 Comm'tssion'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.
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. 67 and the Environmental Protection Plan con-tained in Appendix B, are hereby incorporated in the license.
PP8L shall operate the facility in accordance with the Technical Specifica-tions and the Environmental Protection Plan.
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3.
This license amendment is effective as of its date of issuance to be implemented by October 1, 1987.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 17, 1987 Robert E. Mart~ /s/ for Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II P
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en 87 PDI-2/PM MThadani:ca
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3.
This license amendment is effective as of its date of issuance to be implemented by October 1, 1987.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 17< l987
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Project Directorate I-2 Division of Reactor Projects I/II
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ATTACHMENT TO LICENSE AMENDMENT NO. 67 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 page is identified by Amendment number and contains vertical 'lines indicating the areas of change.
The overleaf page is provided to maintain document completeness.*
REMOVE 3/4 7-11*
3/4 7-12 INSERT 3/4 7-11*
3/4 7-12
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PLANT SYSTEMS SURVEILLANCE RE UIREMENTS b.
Visual Ins ection Acce tance Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERA8ILITY, (2) that attachments to the foundation or supporting structure are secure, and (3) in those locations where snubber movement can be manually induced without disconnecting the snubber, that the snubber has freedom of movement and is not frozen up.
Snubber s which appear inoperable as a result of these visual inspections may be determined OPERA8LE for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible, and (2) the affected snubber is functionally tested in the as found condition and determined OPERA8LE per Surveillance Requirements 4.7.4. d.
c.
Functional Tests Ouring the first refueling shutdown and at least once per 18 months thereafter during shutdown, a representative sample of at learnt that number of snubbers which follows the expression 35 (1 + -)
2 where c = 4, is the allowable number of snubbers not meeting the acceptance criteria selected by the. operator, shal,l be functionally tested either in-place ot in a bench test.
For each number of snubbers above c which does not meet the functional test accept-ance criteria of Specifications 4.7.4.d.,
an additional sample selected according to the expression 35 (1 + -) (
)
(a - c) shall 2
c+1 be functionally tested, where a is the total number of snubbers found inoperable during the functional testing of the representative sample.
~ Functional testing shall continue according to the expression b [35 (1+ <) (
+ >) ) where b is the number 'of snubbers found inoper c
2 2
able in the previous re-sample, until no additional inoperable
. are found within a sample or until all snubbers have been functionally tested.
The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of'nubbers.
At least 25K of the snubbers in the representative sample shall include snubbers from the following three categories:
2.
3.
The first snubber away from each reactor vessel nozzle.
Each snubber within 5 feet of heavy equipment,
- valve, pump, turbine, motor, etc.
Each snubber within 10 feet of the discharge from a safety relief valve.
SUSQUEHANNA - UNIT 1 3i4 7-11 Amendment No.
63 APR 6
198"s
PLANT SYSTEMS
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SURVEILLANCE RE UIREMENTS (Continued}
Functional Test (Continued)
In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next test period.
If.a spare snubber has been installed in place of a failed snubber, then both the failed snubber, if it is repaired and installed in another
- position, and the spare snubber shall be retested.
Test results of these snubbers may not be included for the re-sampling.
If any snubber selected for functional testing either fails to lockup or fails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency all snubbers of the same design subject to the same defect shall be functionally tested.
This testing requirement shall be independent of the require-ments stated above for snubbers not meeting the functional test acceptance criteria.
For any snubber(s) found inoperable, an engineering evaluation shall be performed on the components which are supported by the snubber(s).
The purpose of this engineering evaluation shall be to determine if the components supported by the snubber(s) were adversely affected by the inoperability of snubber(s) in order to ensure that the supported component remains capable of meeting the designed service.
d.
Mechanical Snubbers Functional Test Acce tance Criteria The mechanical snubber functional test shall verify that:
1..
The force that initiates free movement of the snubber rod in either tension or compression is less than the specified maximum drag force.
2.
Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.
3.
Snubber release
- rate, where required, is within the specified range in compression or tension.
For snubbers specifically required not to displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.
SUS(UEHANNA - UNIT 1 3/4 7-12 Amendment No.
67