ML20149C867
| ML20149C867 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 01/22/1988 |
| From: | Virgilio M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20149C871 | List: |
| References | |
| NUDOCS 8802090329 | |
| Download: ML20149C867 (7) | |
Text
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g S* KFCg UNITED STATES
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CLEVELAND ELECTRIC ILLUMINATING COMPANY. ET AL DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT, UNIT NO. 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No.10 License No. NPF-58 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Cleveland Electric Illuminating Company, Duquesne Light Company, Ohio Edison Company, Pennsylvania Power Company, and Toledo Edison Company (the licensees) dated September 11, 1987, as amended September 18, 1987, and supplemented t
January 8, 1988, 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; B.
The facility will operate in conformity with the application, the l
provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorizdd*by this amendment can be conducted without enjangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; 0.
The issuance of this amendment will not be inimical to the common defense and security or to the health anc safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Conmission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changts to the Technical Specifications 4
as indicated in the attachment to this licente amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-58 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A and the Environ-mental Protection Plan contained in Appendix 8, as revised through Amendment No.10, are hereby incorporated into this license.. Cleveland Electric Illuminating Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
8802090329 880122 l
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This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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k Martin J. Virgilio, Director Project Directorate III-1 Division of Reactor Projects - III, IV, V
& Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 22, 1988
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ATTACHMENT TO LICENSE AMEN 0 MENT NO.
10 FACILITY OPERATING LICENSE NO. NPF-58 O_0CKET NO. 50-440 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Overleaf page(s) provided to maintain document completeness.
Remove Insert 3/4 4-11 3/4 4-11 3/4 6-5 3/4 6-5 3/4 6-Sa W
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.3.2.1 The reactor coolant system-leakage shall be demonstrated to be within each of the above limits by:
Monitoring the drywell atmospheric particulate or gaseous radioactiv-a.
ity at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (not a means of quantifying leakage),
b.
Monitoring the drywell floor and equipment sump flow rate at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, Monitoring the drywell upper drywell air coolers condensate flow rate c.
at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and d.
Monitoring the reactor vessel head flange leak detection 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 />.
i 4.4.3.2.2 Each reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1 shall be demonstrated OPERABLE by leak testing pursuant to-Specification 4.0.5 and verifying the leakage of each valve to be within the
)
specified limit:
At least once per 18 months,**
a.
i b.
Prior to returning the valve to service following maintenance, repair or replacement work on the valve which could affect its
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leakage rate, and
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The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 3.
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i 1
1 i
- P.I.V. leak test extension to the first refueling outage is permissible for each Reactor Coolant System P.I.V. listed in Table 3.4.3.2-1, which are identified in letter PY-CEI/NRR-0714L (dated September 11, 1987) as needing a plant outage to test.
For this one time test interval, the provisions of Specification 4.0.2 are not applicable.
PERRY - UNIT 1 3/4 4-11 Amendment No.10
TABLE 3.4.3.2-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES VALVE NUMBER SYSTEM 1C41-F006 Standby Liquid Control IC41-F007 Standby Liquid Control 1E12-F008 Residual Heat Removal 1E12-F009 Residual Heat Removal i
1E12-F041A Residual Heat Removal i
1E12-F0418 Residual Heat Removal i
1E12-F0410 Residual Heat Removal 1E12-F0427 Residual Heat Removal 1E12-F042B Residual Heat Removal IE12-F042C Residual Heat Removal 1E12-F550 Residual Heat Removal IE21-F005 Low Pressure Core Spray 1E21-F006 Low Pressure Core Spray 1E22-F004 High Pressure Core Spray 1E22-F005 High Pressure Core Spray 1E51-F065 Reactor Core Isolation Cooling 1E51-F066 l
Reactor Core Isolation Cooling l
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PERRY - UNIT 1 3/4 4-12
y CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 1.
Confirms the accuracy of the test by verifying that_ the differ-ence between the supplemental data and the Type A test data is within 0.25 L.
The formula to be used is:
a 1
[L
+L
- 0.25 L 3 1 lcib* lam f 0.25 L ] where L o
am a
o a
c supplemental test result; L = superimposed leakage; 13,=
g measured Type A. leakage.
2.
Has duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.
3.
Requires the quantity of gas injected into the primary contain-ment or bled from the primary containment during the supple-mental test to be between 0.75 L and;1.25 L
- l a
a d.
Type B and C tests shall be conducted with gas at P, 11.31 psig*,
at intervals no greater than 24 months # except for fests involving:
1.
Air locks,
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2.
Main steam line isolation valves, l
3.
Valves pressurized with fluid from a seal system, 4.
All containment isolation valves in hydrostatically tested lines per Table 3.6.4-1 which penetrate the primary containment, and 5.
Purge supply and exhaust isolation valves with resilient material seals.
7.,,
Air locks shall be tested and demonstrated OPERABLE per Surveill'ance e.
l Requirement 4.6.1.3.
f.
Main steam line isolation valves shall be leak tested at least once i
l per 18 months.**
1 i
9 Leakage from isolation valves that are sealed with fluid from a seal system may be excluded, subject to the provisions of Appendix J of 10 CFR 50 Section III.C.3, when determining the combined leakage rate l
provided the seal system and valves are pressurized to at least l
1.10 P maintain,12.44psig,andthesealsystemcapacityisadequateto system pressure for at least 30 days, h.
All containment isolation valves in hydrostatically tested lines per Table 3.6.4-1 which penetrate the primary containment shall be leak tested at least once per 18 months.#
"Unless a hydrostatic test is required per Table 3.6.4-1.
- Except for valves 1821-F022A and 1821-F028A, which shall be leak tested prior to July 12, 1987.
This exception expires on July 12, 1987.
1
- A Type C test interval extension to the first refueling outage is permissible for primary containment isolation valves listed in Table 3.6.4-1, which are identified in letter PY-CEI/NRR-0714 L (dated September 11,1987) as needing a plant outage to test.
For this one time test interval, the provisions of Specifi<ation 4.0.2 are not applicable.
1 PERRY - UNIT 1 3/4 6-5 Amendment No. 5, 10
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j CONTAltiMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) i.
Purge supply and exhaust isolation valves with resilient material seals shall be tested and demonstrated OPERABLE per Surveillance Requirements 4.6.1.8.3. and 4.6.1.8.4.
j.
The provisions of Specification 4.0.2 are not applicable to Specifications 4.6.1.2.a, 4.6.1.2.b, 4.6.1.2.c, and 4.6.1.2.d.
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- 7'.
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l (Next pace is 3/4 6-6.)
PERRY - UNIT 1 3/4 6-5s Amendment No. 10
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