ML20082C478
| ML20082C478 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/11/1991 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duquesne Light Co, Ohio Edison Co, Pennsylvania Power Co |
| Shared Package | |
| ML20082C483 | List: |
| References | |
| DPR-66-A-158, NPF-73-A-037 NUDOCS 9107190137 | |
| Download: ML20082C478 (9) | |
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g DUQUESNE LIGHT COMPANY OH10EDISONCOM1ANJ DENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLFY POWER STATION, UNIT NO. 1, AliENDMENT TO FACILITY OPERATING LICENSE 4
Amendment No.158 License No. DPR-66
- 1. -The__ Nuclear Regulatory Comission (the Commission).has found that:
-A.
The application for amendment by Duquesne Light Company, et. al.
the-licensee)datedFebruary20,-1991, complies with the standards-and requirements of_ the Atomic Energy Act of 1954, as amended (the Act) and the.cosaission's rules and regulations set forth in 10 CFR Chapter.I;_
j B.-
The facility will operate.in conformity with the application, the provisions _ of the Act, and the rules and ~ regulations of the Comissior ; -
I-C.
- There is reasonable assurance.(i) that the acth ities 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 Comission's regulations; V
E 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, l
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9107190137 910711 ADOCK 05000334 PDR PDR l - L P
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, 2.
Accordingly, the license is amended by changes to the Technici Specifications as indicated in the attachment to this license e ' ' ment, and paragraph 2.C.(2) of Facility Operating icense No. DPR-66, ' hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.158, are hereby incorporated in the license.
The licensee shell operate the facility in accordance with the Technical Specifications.
3.
This license amendment is etfective as nf the date of its issucnce, to be implemented within 60 days of i: suance.
FOR TiiE NUCLEAR REGd TORY COMMISSION r7 Job F. Stolz, Director P ject Directorate 1-4 ivision of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Chances to the Technical Specifications Date of Issuance: July 11,1991 l
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ATTACHMENT TO LICENSE AtiENCMENT NO.158 FACILITY OPERATING LICENSE NO. DPR-66 00CKET NO. 50-334 Rr;1 ace the'following page of Appendix A, Technical Specifications, with the enclosed page as indicated.
The revised page is identified by amendment nur.iber and contain vertical lines indicating the areas of change.
Remove Insert 3/4 6-2 3/4 6-2 l-l l
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CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of:
1.
L, 0.10 percent by weight of the containment air per 34 hours3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> at P, (40.0 psig), or o
b.
A combined leakage rate of 5 0.60 L for all penetrations a
and valves subject to Type B and C tests as identified in Table 3.6-1, when pressurized to P
- a APLICABILITY:
MODES 1, 2,
3 and 4.
ACTION:
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L,
or (b) with the measured combined leakage g
rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 L,
restore the leakage rate (s) to within the a
limit (s) prior to increasing the Reactor Coolant System temperature above 200*F.
4 SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakt 1e rates shall be demonstrated at the following test schedu and maall be determined in-accordance with Appendix J of 10 CFR 50}e:
a.
A Type-A test (Overall Integrated Containment Leakage Rate) shall be conducted at 40 1
10-month intervals during shutdown at Pa (40.0 psig).
i Exemption to Appendix J of 10 CFR 50, Scction III.D.l(a),
granted on December 5, 1984 BEAVER VALLEY - UNIT 1 3/4 6-2 Amendment 87, 143, 158
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UNITED STATES i
NUCLEAR REGULATORY COMMISSION o\\
'"f WASHINGTON. D.C. F456 f..-:.c.4 DUQUESNE LIGHT COMPANY OH10 EDISON COMPANY THE CLEVELAND ELECTRIC ILLUMINATitlG COMPANY THE TOLEDO EDIS0N COMPANY DOCKET NO. 50-412 BFAVER VALLEY POWER STATION, UNIT NO. 2 AMENDMENT TO EACILITY OPERATING LICENSE Amendment No. 37 License No. NPF-73 1.
The Muclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Duquesne Light Company, et. al.
(the licensee) dated February 20, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as ame.uded (the Act) and the Comission's rules and 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 rules and regulations of the Comission; 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 Comission's regulations; D.
The issuance of this ansendment 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 Comission's regulations and all applicable requirements have been satisfied.
l
. 2.
Accordingly, the licensee is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-73 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 37
, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. DLC0 shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULA ORY COMMISSION
//
4?
f, Joh
. Stolz, Director Pr ject Directorate I-4 vision of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 11,1991
li ATTACHMENT TO LICENSE AMENDMENT NO. 37 FAC11.1TY OPERATitiG LICENSE NO. DPR-73 DOCKET NO. 50-412 Replace the following page of Appendix A, Technical Specifications, with the enclosed page as indicated. "
revised page-is identified by amendment number and contain vertical
.s indicating the areas of change.
Remove Insert 3/4 6-?
3/4 6-2 l
3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION
- 3. 6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY:
H0 DES 1, 2, 3 and 4.
ACTION:
Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
SURVEILLANCE _SEOUIREMENTS l
- 4. 6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
At least once per 31 days by verifying that:
a.
1.
All penetrations
- not capable of being closed by OPERABLE contain-ment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 3.6-1 of Specification 3.6.3.1.
2.
All equipment hatches are closed and sealed.
b.
By verifying that each containment air lock is OPERABLE per Specification 3.6.1.3.
- Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed or otherwise secured in the closed position.
These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.
BEAVER VALLEY - UNIT 2 3/4 6-1
CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of < L, 0.10 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P,a (44.7 psig).
b.
A combined leakage rate of < 0.60 L for all penetrations and a
valves subject to Type B and C tests as identified in Table 3.6-1, when pressurized to P, (44.7 psig).
APPLICABILITY: H0 DES 1, 2, 3 and 4.
ACTION:
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L, or (b) with the measured combined leakage rate for all a
penetrations and valves subject to Types B and C tests exceeding 0.60 L,,
-restore the leakage rate (s) to within the limit (s) prior to increasing the 1 Reactor Coolant System temperature above 200*F.
SURVEILLANCE REOUIREMENTS 4.6.1.2' The containment. leakage rates shall be demonstrated at the following test schedule and shall be determined in accordance with Appendix J of 10 CFR 50:
f a.
A Type-A test (Overall-Integrated Containment Leakage Rate) shall be conducted at 40 1 10-month-intervals during shutdown at P*
(44.7 psig).
b.
If any Periodic Type A test fails to meet 0.75 L,, the test schedule l
for subsequent Type A tests shall be reviewed and approved by the Commission. If two consecutive Type A tests fail to meet 0.75 L,,
a Type A to.st shall be performed at least every 18 months until two-consecutive Type A tests meet 0.75 L, at which time the above test-t schedule may be resumed.
BEAVER VALLEY - UNIT 2 3/4 6-2 Amendment No. H, 37
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