ML20078M969
| ML20078M969 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 11/29/1994 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Philadelphia Electric Co |
| Shared Package | |
| ML20078M973 | List: |
| References | |
| NPF-39-A-082, NPF-85-A-043 NUDOCS 9412050313 | |
| Download: ML20078M969 (8) | |
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4 UNITED STATES 2-E NUCLEAR REGULATORY COMMISSION i
I*
f WASHINGTON, D.C. 205d64001
.....,o PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-352 LIMERICK GENERATING STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE f
Amendment No. 82 License No. NPF-39 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company (the i
licensee) dated January 14, 1994, as supplemented by letters dated March 22, July 14, September 1, October 21, and November 22, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and 1
regulations set forth in 10 CFR Chapter I; r
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the i
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; 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 ht.ve been satisfied.
i 6
L 9412050313 941129
[
PDR ADOCK 05000352 P
. 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.(2) of Facility Operating License No. NPF-39 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.
82, are hereby incorporated into this license.
Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION n F. Stolz, Dire tor oject Directora e I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 29, 1994
ATTACHMENT TO LICENSE AMENDMENT NO. 82 FACILITY OPERATING LICENSE NO. NPF-39 DOCKET NO. 50-352 Replace the following page of the Appendix A Technical Specifications with the attached page.
The revised page is identified by Amendment number and contains vertical lines indicating the area of change.
Remove Insert 5-8 5-8 f
1
__l I
DESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE (Continued) b.
For.a pressure of:
1.
1250 psig on the suction side of the recirculation pump.
2.
1500 psig from the recirculation pump discharge to the outlet side of the discharge shutoff valve.
3.
1500 psig from the discharge shutoff valve to the jet pumps.
c.
For a temperature of 575'F.
VOLUME l
5.4.2 The total water and steam volume of the reactor vessel and recirculation
. system is approximately 22,400 cubic feet at a nominal steam dome saturation temperature of 547'F.
{
5.5 FUEL STORAGE CRITICALITY l
5.5.1.1 The spent fuel storage racks are designed and shall be maintained with:
a.
A k.,, equivalent to less than or equal to 0.95 when flooded with unborated water, including all calculational uncertainties and biases as described in Section 9.1.2 of the FSAR.
b.
A nominal center-to-center distance between fuel assemblies placed in the storage racks of greater than or equal to 6.244 l
l inches.
5.5.1.2 The k.,, for new fuel for the first core loading stored dry in the spent fuel storage racks shall not exceed 0.98 when aqueous foam moderation is assumed.
DRAINAGE 5.5.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 346'0".
1 CAPACITY 5.5.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 4117 fuel assemblies.
l 5.6 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.6.1 The components identified in Table 5.6.1-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.6.1-1.
LIMERICK - UNIT 1 5-8 Amendment No. 72, 82 L.
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t UNITED STATES J
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20566 0001 l
'+9..... $
PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-353 LIMERICK GENERATING STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 43 License No. NPF-85 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
Tha application for amendment by Philadelphia Electric Company (the licensee) dated January 14, 1994, as supplemented by letters dated-March 22, July 14, September 1, October 21, and November 22, 1994, complies with the standards and requirements of the Atomic Energy Act i
of IM4, 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 provisions of the Act, and the rules and 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; 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 Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-85 is hereby amended to read as follows:
Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.
43, are hereby incorporated into this license.
Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION h
Stolz, Direc r ject Directorat
-2 ivision of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: November 29, 1994
ATTACHMENT TO LICENSE AMENDMENT N0. 43 FACILJTY OPERATING LICENSE NO. NPF-85 DOCKET NO. 50-353 Replace the following page of the Appendix A Technical Specifications with the attached page. The revised page is identified by Amendment number and contains vertical lines indicating the area of change.
Remove Insert 5-8 5-8 P
(
L
DESIGN FEATURES
~
DESIGN PRESSURE AND TEMPERATURE (Continued) b.
For a pressure of:
1.
1250 psig on the suction side of the recirculation pump.
2.
1500 psig from the recirculation pump discharge to the outlet side of the discharge shutoff valve.
3.
1500 psig from the discharge shutoff valve to the jet pumps.
c.
For a temperature of 575*F.
VOLUME 5.4.2 The total water and steam volume of the reactor vessel and recirculation system is approximately 22,400 cubic feet at a nominal steam dome saturation temperature of 547'F.
5.5 FUEL STORAGE CRITICALITY 5.5.1.1 The spent fuel storage racks are designed and shall be maintained with:
a.
A k,,, equivalent to less than or equal to 0.95 when flooded with unborated water, including all calculational uncertainties and biases as described in Section 9.1.2 of the FSAR.
b.
A nominal center-to-center distance between fuel assemblies placed in the storage racks of greater than or equal to 6.244 inches.
5.5.1.2 The k,,, for new fuel for the first core loading stored dry in the spent fuel storage racks shall not exceed 0.98 when aqueous foam moderation is assumed.
DRAINAGE 5.5.2 Tha spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 346'0".
CAPACITY 5.5.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 4117 fuel assemblies.
l 5.6 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.6.1 The components identified in Table 5.6.1-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.6.1-1.
LIMERICK - UNIT 2 5-8 Amendment No. 43