ML20215E180

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Amend 29 to License NPF-22,deleting Applicability of Tech Spec 3.0.4 for Purposes of Entering Operational Condition 5 from Defueled Condition During First Refueling Outage
ML20215E180
Person / Time
Site: Susquehanna Talen Energy icon.png
Issue date: 10/06/1986
From: Adensam E
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20215E172 List:
References
NUDOCS 8610150095
Download: ML20215E180 (5)
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k g UNITED STATES NUCLEAR REGULATORY COMMISSION y -l WASHINGTON, D. C. 205f 5 PENNSYLVANIA POWER & LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE, INC.

DOCKET NO. 50-388 SUSOUEHANNA STEAM ELECTRIC STATION, UNIT P AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 29 License No. NPF-?2

1. The Nuclear Regulatory Commission (the Commission or the NRC) has found that:

A. The application for the amendment filed by the Pennsylvania Power A Light Company, dated September 12,1986,(PLA-2710 and PLA-2770) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; F. The facility will operate in conformity with the application, the provisions of the Act, and the 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 Commission's regulations set forth in 10 CFR Chapter I; 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 Tecnnical Specifica-l tions as indicated in the attachment to this license amendment and paracraph l

2.C.(2) of the Facility Operating License No. NPF-22 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan i

The Technical Specifications contained in Appendix A, as revised I through Amendment No. 29 and the Environmental Protection Dlan con-tained in Appendix B, are hereby incoroorated in the licers.,

PP&L

shall operate the facility in accordance with the Technical Specifica-l tions and the Environmental Protection Plan.

0610150095 861006 PDR ADOCK 05000388 PDR

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3. This amendment was effective as of September 13, 1986.

FOR THE NUCLEAR REGULATORY COMMISSION b --

Elinor G. Adensam, Director BWR Pro; lect Directortte No. 3 Division of.RWR Licensing

Enclosure:

Changes to the Technical Specifications Date of Issuance: October 6, 1986 i

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ATTACHMENT TO LICENSE AMENDMENT NO. 29 -

FACILITY OPERATING LICENSE NO. NPF-22 ..

DOCKET NO. 50-388 Replace the followinc page of the Appendix "A" Technical Specifications with the enclosed page. The revised pace is identified by Amendment number and contains vertical lines indicating the area of change. The correspondinc overleaf page is also provided to maintain document completeness.

REMOVE INSERT 3/4 9-17 3/4 9-17 3/4 9-18 3/4 9-1P- (overleafi l

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REFUELING OPERATIONS 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION HIGH WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.11.1 At least one shutdown cooling mode loop of the residual heat removal (RHR) system shall be OPERABLE and in operation

  • with at least:
a. One OPERABLE RHR pump, and
b. One OPERABLE RHR heat exchanger.

APPLICABILITY: OPERATIONAL CONDITION 5, when irradiated fuel is in the reactor vessel and the water level is greater than or equal to 22 feet above the top of the reactor pressure vessel flange.

ACTION:

a. With no RHR shutdown cooling mode loop OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter, demonstrate the operability of at

, least one alternate method capable of decay heat removal. Otherwise, suspend all operations involving an increase in the reactor decay

heat load and establish SECONDARY CONTAINMENT INTEGRITY within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
b. With no RHR shutdown cooling mode loop in operation, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish reactor coolant circulation by an alternate method and monitor reactor coolant temperature at least once per hour.
c. The provisions of Specification 3.0.4 are not applicable for the purposes of entering 3PERATIONAL CONDITION 5 from a defueled condition during the first refueling and inspection outage.

SURVEILLANCE REQUIREMENTS 4.9.11.1 At least one shutdown cooling mode loop of the residual heat removal system or alternate method shall be verified to be in operation and circulating l reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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  • The shutdown cooling pump may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8-hour period.

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SUSQUEHANNA - UNIT 2 3/4 9-17 Amendment 29

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REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDITION FOR OPERATION ,,

3.9.11.2 Two shutdown cooling mode loops of the residual heat removal (RHR) system shall be OPERABLE and at least one loop shall be in operation,* with each loop consisting of at least:

a. One OPERABLE RHR pump, and
b. One OPERABLE RHR heat exchanger.

APPLICABILITY: OPERATIONAL CONDITION 5, when irradiated fuel is in the reactor vessel and the water level is less than 22 feet above the top of the reactor pressure vessel flange.

ACTION:

a. With less than the above required shutdown cooling mode loops of the RHR system OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter, demonstrate the operability of at least one alternate method capable of decay heat removal for each inoperable RHR shutdown cooling mode loop.
b. With no RHR shutdown cooling mode loop in operation, within I hour establish reactor coolant circulation by an alternate method and monitor reactor coolant temperature at least once per hour.

l SURVEILLANCE REQUIREMENTS 4.9.11.2 At least one shutdown cooling mode loop of the residual heat removal system or alternate method shall be verified to be in operation and circulating rzactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

"The shutdown cooling pump may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8-hour period.

SUSQUEHANNA - UNIT 2 3/4 9-18

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