ML20209C240
| ML20209C240 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/31/1987 |
| From: | Nerses V Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20209C245 | List: |
| References | |
| NUDOCS 8704280627 | |
| Download: ML20209C240 (10) | |
Text
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wasmwarow.o.c. zones PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 77 License No. DPR-70 I.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Public Service Electric and Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated February 6,1986 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; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
Thereisreasonableassurance(i)thattheactivitiesauthorizedby j
this amendment can be conducted without endangering the health and safety of the public, and (11) 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 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.
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, 1
and paragraph 2.C.(2) of Facility Operating License No. DPR-70 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 77, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION ictor Nerses, Acting Director PWR Project Directorate #5 Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance: March 31, 1987 P
i I
ATTACHMENT TO LICENSE AMENDMENT NO. 77 FACILTIY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
Remove Pages Insert Pages 3/4 9-6 3/4 9-6 3/4 9-7 3/4 9-7
REFUELING OPERATIONS MANIPULATOR CRANE OPERABILITY LIMITING CONDITION FOR OPERATION 3.9.6 The manipulator crane and auxiliary hoist shall be used for movement of control rods or fuel assemblies and shall be OPERABLE with:
a.
The manipulator crane used for movement of fuel assemblies having:
1.
A minimum capacity of 3250 pounds, and 2.
An overload cut off limit less than or equal to 2850 pounds.
b.
The auxiliary hoist used for movement of control rods having:
1.
A minimum capacity of 700 pounds, and 2.
A load indicator which shall be used to prevent lifting loads in excess of 600 pounds.
APPLICABILITY:
During movement of control rods or fuel assemblies within the reactor pressure vessel.
ACTION:
With the requirements for crane and/or hoist OPERABILITY not satisfied, suspend use of any inoperable manipulator crane and/or auxiliary hoist from operations involving the movement of control rods and fuel assemblies within the reactor pressure vessel. The provisions of Specification 3.0.3 are not cpplicable.
SURVEILLANCE REQUIREMENTS 4.9.6.1 Each manipulator crane used for movement of fuel assemblies within the reactor pressure vessel shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> 1
i prior to the start of such operations by performing a load test of at least 3250 pounds and demonstrating an automatic load cut off set at less than or cqual to 2850 pounds; this includes the heavy load plus the weight of the l
. crane mast and gripper.
~
l 4.9.6.2 Each auxiliary hoist and associated load indicator used for movement of control rods within the reactor pressure vessel shall be demonstrated
'by.performin 0PERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of such operations g a load test of at least 700 pounds.
SALEM - UNIT 1 3/4 9-6 JWnen&nent No. 77 t
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REFUELING OPERATIONS CRANE TRAVEL - FUEL HANDLING AREA LI'MITING CONDITION FOR OPERATION 3.9.7 Loads in excess of 2200 pounds shall be prohibited from travel over j
fuel assemblies in the storage pool.
APPLICABILITY:
Mth fuel assemblies in the storage pool.
ACTION:
With the-requirements of the above specificatio'n not satisfied, place the crane load in a safe condition. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.7 The overload cutoff which prevents crane travel with loads in excess of 2200 pounds over fuel assemblies shall be demonstrated OPERABLE within 7 days prior to crane use and at least one per 7 days thereafter during the crane operation.
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SALEM - UNIT 1 3/49-7 Amen &nent No. 77 I
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
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1 PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY
. ATLANTIC CITY ELECTRIC COMPANY DOCKET N0. 50-311 SALEM NUCLEAR GENERATING STATION UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 51 License No. DPR-75 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Public Service Electric and Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated February 6,1986 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; 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 Consiission's regulations; D.
The issuance of this amendment will not be inimical to the cosmon 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 Connission's regulations and all applicable requirements have been satisfied.
t
9 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.2 of Facility Operating License No. DPR-75 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 51, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Victor Nerses, Acting Director PWR Project Directorate #5 Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance: March 31, 1987 t
e I
i ATTACHMENT TO LICENSE AMENDMENT NO. si FACILTIY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
Remove Pages Insert Pages 3/4 9-6 3/4 9-6 3/4 9-7 3/4 9-7
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I REFUELING OPERATIONS MANIPULATOR CRANE OPERABILITY LIMITING CONDITION FOR OPERATION i
3.9.6 The manipulator crane and auxiliary hoist shall be used for movement 1
of control rods or fuel assemblies and shall be OPERABLE with:
)
l' a.
The manipulator crane used for movement of fuel assemblies having:
i 1.
A minimum capacity of 3250 pounds, and i
2.
An overload cut off limit less than or equal to 2850 pounds.
b.
The auxiliary hoist used for novement of control rods having:
1.
A minimum capacity of 700 pounds, and 2.
A load indicator which shall be used to prevent lifting loads in excess of 600 pounds.
APPLICABILITY: During novement of control rods or fuel assemblies within the reactor pressure vessel.
i i
ACTION:
With the requirements for crane and/or hoist OPERABILITY not satisfied, suspend use of any inoperable manipulator crane and/or auxiliary hoist from operations involving the movement of control rods and fuel assemblies within the reactor pressure vessel. The provisions of Specification 3.0.3 are not applicable.
t SURVEILLANCE REQUIREMENTS 4.9.6.1 Each manipulator crane used for movement of fuel assemblies within the reactor pressure vessel shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of such operations by performing a load test of at least
- 3250 pounds and demonstrating an automatic load cut off set at less than or cqual to 2850 pounds; this includes the heavy load plus the weight of the crane mast and gripper.
'l l
4.9.6.2 Each auxiliary hoist and associated load indicator used for novement of control rods within the reactor pressure vessel shall be i
demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of such operations
'by-performing a load test of at least 700 pounds.
SALEM - UNIT 2 3/4 9-6 Amendment It. 51
REF0ELING OPERATIONS CRANE TRAVEL - FUEL HANDLING AREA LI'NITING CONDITION FOR OPERATION 3.9.7 Loads in excess of 2200 pounds shall be prohibited 'from travel over l
fuel assemblies in the storage pool.
APPLICABILITY:
iftth fuel assemblies in the storage pool.
ACTION:
lilth the requirements of the above' specification not satisfied, place the crane load in a safe condition. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REgllREMENTS 4.9.7 The overload cutoff which prevents crane travel with loads in excess of 2200 pounds over fuel assemblies shall be demonstrated OPERABLE within 7 days prior to crane use and at least one per 7 days thereafter during the crane operation.
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SALEM - UNIT 2 3/4 9-7 Anandment No. 51 t
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