ML20100K099
| ML20100K099 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 02/23/1996 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Philadelphia Electric Co |
| Shared Package | |
| ML20100K102 | List: |
| References | |
| NPF-39-A-114, NPF-85-A-076 NUDOCS 9603010037 | |
| Download: ML20100K099 (8) | |
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- g UNITED STATES
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NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 2008H001 l'
- %...../
PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-352 LIMERICK GENERATING STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No.114 License No. NPF-39 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Philadelphia Electric Company (the licensee) dated August 1,1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
I 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 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 conducted in compliance with the Comission's regulations; 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.
i 1
9603010037 960223 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 Snecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.114
, 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, and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION byhl JohnJh Stolz, Director i
PrQ4ct Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications i
Date' of Issuance: February 23, 1996 4
l 1
l ATTACHMENT TO LICENSE AMENDMENT NO.114 l
EACILITY 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 3/4 9-1 3/4 9-1 i
l
i 3.4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR MODE SWITCH l*
LIMITING CONDITION FOR OPERATION l
l-3.9.1 The reactor mode switch shall be OPERABLE and locked in the Shutdown or i
l Refuel position. When the reactor mode switch is locked in the Refuel position:
a.
The Refuel position one-rod-out interlock shall be OPERABLE.
b.
The following Refuel position interlocks shall be OPERABLE:
- 1. All rods in.
l
- 2. Refuel Platforr, (over-core) position.
l i
- 3. Refuel Platform hoists fuel-loaded.
- 4. Serviice Platform hoist fuel-loaded l
(with Service Platform installed).
l APPLICABILITY: OPERATIONAL CONDITION 5* **.
ACTION:
a.
With the reactor mode switch not locked in the Shutdown or Refuel l
l positiors as specified suspend CORE ALTERATIONS and lock the reactor mode swit.ch in the Shu,tdown or Refuel position.
l b.
With the one-rod-out interlock inoperable,ities of all control rods ***,
verify all control rods are fully inserted and disable withdraw capabil or lock the reactor mode switch in the Shutdown position.
c.
With any of the above required Refuel Platform Refuel position interlocks ALTERATION $. take one of the ACTIONS listed below, or suspend CORE inoperable 1.
Verify control rods are fully inserted and disable withdraw capabilities of all control rods ***, or Verify ) Refuel Platform is not over-core (limit switches not 2.
reached and disable Refuel Platform travel over-core, or l
3.
Verify that no Refuel Platform hoist is loaded and disable all Refuel Platform hoists from picking up (grappling) a load.
d.
With the service Platform installed over the vessel and any of the above required Service Platform Refuel position interlocks inoperable, take one of the ACTIONS listed below, or suspend CORE ALTERATIONS.
1.
Verify all control rods are full 5** inserted and disable withdraw l
capabilities of all control rods
, or 2.
Verify Service Platform hoist is not loaded and disable Service i
Platform hoist from picking up (grappling) a load.
See Special Test Exceptions 3.10.1 and 3.10.3.
The reactor shall be maintained in OPERATIONAL CONDITION 5 whenever fuel is in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
Except control rods removed per Specification 3.9.10.1 or 3.9.10.2.
l LIMERICK - UNIT 1 3/4 9-1 Amendment No. 114 I
'p ** hg g*
UNITED STATES NUCLEAR REGULATORY COMMISSION f
WA5HINGTON, D.C. 306664 201
%,.....f PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-353 LIMERICK GENERATING STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.76 License No. NPF-85 1.
The Nuclear Regulatory Comission (the Comission) has found that:
j A.
The application for amendment by Philadelphia Electric Company (the licensee) dated August 1, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission's rules and regulations set forth in 10 CFR Chapter I; i
B.
The facility will operate in conformity with thi 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 i
this amendment can be conducted without endangering the health and l
safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; 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
l i
l 1 ;
l 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, j
and paragraph 2.C.(2) of Facility Operating License No. NPF-85 is hereby i
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. 76
, are hereby incorporated into this license.
Philadelphia Electric Company shall operate the facility 'n accordance l
with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance, and shall be implemeted within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
\\
Johrt f. Stolz, Director
/
Pr6 ject Directorate 1-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 23, 1996 I
i
{
l
ATTACMENT TO LICENSE AMENDMENT NO. 76 FACILITY OPERATING LICENSE NO. NPF-85 QQCKET NO. 50-353 I
l Replace the following page of the Appendix A Technical Specifications with the attached page. The revised page is identified by Amendment number and contaisis vertical lines indicating the area of change.
Remove Insert 3/4 9-1 3/4 9-1 l
l l
l l
l 3.4.9 REFUELING OPERATIONS
\\
l 3/4.9.1 REACTOR MODE SWITCH LIMITING CONDITION FOR OPERATION 3.9.1 The reactor mode switch shall be OPERABLE and locked in the Shutdown or Refuel position. When the reactor mode switch is locked in the Refuel position:
a.
The Refuel position one-rod-out interlock shall be OPERABLE.
l b.
The following Refuel position interlocks shall be OPERABLE:
l
- 1. All rods in.
l
- 2. Refuel Platform (over-core) position.
l
- 3. Refuel Platform hoists fuel-loaded.
- 4. Service Platform hoist fuel-loaded (with Service Platform installed).
l
?
APPLICABILITY: OPERATIONAL CONDITION 5* **.
ACTION:
a.
With the reactor mode switch not locked in the Shutdown or Refuel position as specified suspend CORE ALTERATIONS and lock the reactor mode switch in the Shu,tdown or Refuel position, b.
With the one-rod-out interlock inoperable,ities of all control rods ***, verify all cont i
fully inserted and disable withdraw capabil or lock the reactor mode switch in the Shutdown position.
)
i c.
With any of the above required Refuel Platform Refuel position interlocks inoperable of the ACTIONS listed below, or suspend CORE ALTERATION $. take one l
1.
Verify control rods are fully
- inserted and disable withdraw capabilities of all control rods **, or Verify ) Refuel Platform is not over-core (limit switches not l
2.
reached and disable Refuel Platform travel over-core, or 3.
Verify that no Refuel Platform hoist is loaded and disable all Refuel Platform hoists from picking up (grappling) a load.
d.
With the Service Platform installed over the vessel and any of the above required Service Platform Refuel position interlocks inoperable, take one of the ACTIONS listed below, or suspend CORE ALTERATIONS.
l.
Verify all control rods are full 5** inserted and disable withdraw capab'ilities of all control rods
, or 2.
Verify Service Platform hoist is not loaded and disable Service Platform hoist from picking up (grappling) a load.
See Special Test Exceptions 3.10.1 and 3.10.3.
The reactor shall be maintained in OPERATIONAL CONDITION 5 whenever fuel is in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
Except control rods removed per Specification 3.9.10.1 or 3.9.10.2.
l i
LIMERICK - UNIT 2 3/4 9-1 Amendment No. 76