ML20141G141
| ML20141G141 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/14/1986 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20141G147 | List: |
| References | |
| NUDOCS 8604230288 | |
| Download: ML20141G141 (5) | |
Text
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION n
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E WASHINGTON. D C. 20555 0000ESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMDANY DOCKET NO. 50-334' BEAVER VALLEY POWER STATTON, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Anendment No.101 License No. DPR-66 1.
The Nuclear Regulatory Comission (the Commissioni has found that:
A.
The application for amendment by Duquesne Light Company, Ohio Edison Company, and Pennsylvania Power Company (the licenseesi dated January 24, 1986, complies with the standards and requirements j
of the Atomic Energy Act of 1454, as amerded Ithe Act) and the j
Commission's rules and regulations set forth in 10 CFR Chapter I:
I B.
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 (1) 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 condu~cted in compliance with the Comission'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 1
E.
The issuance of this amendment is in accordance with 10 CFR Part-51 of the Comission's regulations and all applicable requirements l
have been satisfied.
l 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.(21 of Facility Operatina License No. DPR-66 is hereby amended to read as 4110ws:
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l 8604230288 860414 ADOCK0500g4 PDR P
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(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.101, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This amendment is effective on issuance, to be implemented no later than 30 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Lester S.
ubenstein, Director PWR Project Directorate #2 Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 14,1986 e
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9 ATT/;?HPFNT TO LICENSE ANENDMFNT AMENDMENT NO.101 TO FACILITY OPERATING LICENSE NO. DPR DOCKET NO. 50-334 Revise Appendix A~as follows:
Remove Pages insert Paaes 3/4 3-31 3/4 3-31 3/4 4-14b 3/4 4-14b e
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TABLE 4.3-2 (Contirued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION h
SURVEILLANCE REQUIREMENTS M
CHANNEL MODES IN WHICH E
CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE E
FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED w
4.
STEAM LINE ISOLATION a.
Phnual N.A.
N.A.
M(1) 1, 2, 3, 4 b.
Automatic Actuation Logic N.A.
N.A.
M(2) 1, 2, 3, 4 c.
Containment Pressure--
S R
M 1,2,3 Intermediate-High-High w
ir d.
Steam Line Pressure--Low S
R M
1,2,3 e.
Steamline Pressure Rate-High S
R M
1, 2, 3, 4 l
5.
TURBINE TRIP AND FEEDWATER ISOLATION a.
Steam Generator Water S
R M
1,2,3 Level-High-High a 6.
LOSS OF POWER 0
ij a.
4.16ky Emergency Bus N.A.
R M
1, 2, 3, 4 0
Undervoltage (Loss of H
Voltage) Trip Feed &
g Start Diesel 4
3 b.
4.16Ev and 480v Emergency N.A.
P.
M 1, 2, 3, 4 Bus Undervoltage (Degraded S
Voltage)
' SURVEILLANCE REQUIREMENT (8) on each valve listed in Table 4.4i di3 sha $ak$keaccompS!hedpriortoenteringMode1afterevery l Pe test 4.4.6.3.1 time the plant is placed in the cold shutdown condition for refueling, after each time the plant is placed in a cold shutdown condition for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if testing has not been accomplished in the preceeding 9 months and prior to returning the valve to service after maintenance, repair or replacement work is performed.
4.4.6.3.2 Whenever integrity of a pressure isolation valve listed in Table' 4.4-3 cannot be demonstrated the integrity of the remaining valve in each high pressure line having a leaking valve shall be, determined and recorded daily.
In addition, the position of the other closed valve located in the high pressure piping shall be recorded daily.
(a)
To satisfy ALARA requirements, leakage may be measured indirectly (as from the performance of pressure indicators) if accomplished in accordance with approved procedures and cupported by computations showing that the method is capable of demonstrating valve compliance with the leakage criteria.
BEAVER VALLEY - UNIT 1 3/4 4-14b 9/##f//d%dd/A#ff7/i@l/ISII AMENDMENT NO. 101 i
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