ML20246J497

Amend 38 to License NPF-47,adding Tech Specs for Suppression Pool Pumpback Sys to Tech Spec 3/4.5.3, Suppression Pool

ML20246J497
Person / Time
Site:	River Bend
Issue date:	07/10/1989
From:	Hebdon F Office of Nuclear Reactor Regulation
To:
Shared Package
ML20246J503	List: ML20246J497 ML20246J505
References
NUDOCS 8907170388
Download: ML20246J497 (7)

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UNITED STATES

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%y J GULF STATES UTILITIES COMPANY DOCKET NO.'50-458 RIVER BEND STATION,ilNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.38 1.icense No. NPF-47 1.

The Nuclear. Regulatory Commission (the Comission) has found that:

L A.

The application for amendment by Gulf States Utilities Company (thelicensee)datedAugust 26, 1986 as modified Mcy 2, 1989 and supplemented fiay 25, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (tne Act),

and the Comission's rules and regulations set forth in 10 CFR Chapter I; l

B.

The facility will operate in conformity with the application, as l

amended, the provisions of the Act, and the rules and regulations l-of the. Comission; l

C.

There is reasonable assurance:

(i)thattheactivitiesauthorized l

by this amendment can be conductea 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 license 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.

8907170388 890710 PDR ADOCK 05000458 p

PDC

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. 2.

Accordingly, the lictr.se is amended by changes to the Technical Specificaticr.s as indicated in the attachment to this license amendrent "aragraph 2.C.(2) of Facility Operating License No. NPF-47 is herely ane amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 38 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. GSU shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

The license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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Frederick J. Feboon, Director Project Directorate - IV Division cf Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Charges to the Technical Specifications Date of Issuance: July 10,1989 l

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l ATTACHMENT TO LICEf15E APEf;DMENT tiO. ?8 FACILITY CfERATING LICENSE NO. NPF 47 DOCKETtAD.50-43 1

Replace the following pages of the Appendix "A Technical Specifications with the enclosed pages. The revised pages are identified by Ac.eneraent r.ctber and contain a vertical line indicating the area of change. The cytritaf page is provided to naintain document completeness.

l REMOVE PAGES INSERT PAGES 3/4 5-8 3/4 5-8 3/4 5-9 3/4 5-9 B 3/4 5-3 B 3/4 5-3 l

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EMERGENCY CORE COOLING SYSTEMS j

SURVEILLANCE REQUIREMENTS 4.5.2.1 At least the above required ECCS shall be demonstrated OPERABLE per Surveillance Requirement 4.5.1.

4.5.2.2 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 HPCS system shall be determined OPERABLE by verifying the condensate storage tank required volume when the condensate storage tank is required to be OPERABLE per Specification 3.5.2.e.

RIVER BEND - UNIT 1 3/4 5-7

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EMERGENCY CORE COOLING SYSTEMS ACTION (Continued)

With one SPPS subsystem inoperable, restore the SPPS subsystem to I

c.

OPERABLE status within 31 days or demonstrate the OPERABILITY of the remaining SPPS subsystem at least once per 31 days by:

I 1.

A functional test of the crescent area sump pump, and i

2.

Demonstrating that the associated flow path can be aligned to the suppression pool.

3.

The provisions of Specification 3.0.4 are not applicable.

d.

With both SPPS subsystems inoperable, restore one SPPS subsystem to OPERABLE status within 7 days or:

1.

In OPERATIONAL CONDITION 1, 2, or 3 be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

I-2.

In OPERATIONAL CONDITION 4 or 5* provide at least one alternate l

pumpback method and demonstrate the OPERABILITY of an alternate method within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 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, otherwise suspend CORE ALTERATIONS and all operations that have a potential for draining the reactor vessel and lock the reactor mode switch in the shutdown position.

Establish PRIMARY CONTAINMENT INTEGRITY - FUEL HANDLING within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.5.3.1 The suppression pool shall be determined OPERABLE by verifying the water level to be greater than or equal to, as applicable:

19'6", at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, in OPERATIONAL CONDITION 1, 2 and 3.

l a.

b.

13'3", at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, in OPERATIONAL CONDITION 4 and 5.

4.5.?.2 With the suppression pool level less than the above limit or drained in OPERATIONAL CONDITION 4 or 5*, at least once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s:

Verify the required conditions of Specification 3.5.3.b to be a.

satisfied, or b.

Verify footnote conditions

• to be satisfied.

4.5.3.3 At least once per 92 days, the SPPS shall be demonstrated OPERABLE by:

a.

Verifying each crescent area sump pump develops 50gpm, and b.

Verifying the flow path can be aligned to the suppression pool.

• The suppression pool is not required to be OPERABLE in OPERATIONAL CONDITION 5 provided that the reactor vessel head is removed, the cavity is flooded, the upper containment fuel pool gate is r pen, and the water level is maintained e

within the limits of Specifications 3.9.8 and 3.9.9.

RIVER BEND - UNIT 1 3/4 5-9 Amendment No.33

4 3/4.5 EMERGENCY CORE COOLING SYSTEM BASES SUPPRESSION POOL'(Continued) i Repair work might require making the suppression pool inoperable.

This specification will permit those repairs to be made and at the same time give assurance that the irradiated fuel has an adequate cooling water supply when the suppression pool must be made inoperable, including draining, in OPERATIONAL CONDITION 4 or 5.

In OPERATIONAL CONDITIONS 4 and 5 the suppression pool minimum required water volume is reduced because the reactor coolant is maintained at or below 200*F.

Since pressure suppression is not required below 212*F, the minimum required water volume is based on NPSH, recirculation volume, vortex preven-tion, and a 2' 6" safety margin for conservatism.

The suppression pool pumpback system (SPPS)'is a subsystem designed to ensure suppression pool level; therefore the OPERABILITY of the Suppression l

PSDI can be maintained in the event of a passive ECCS failure.

The ECCS piping components which may experience passive failures will not result in flooding of the ECCS equipment cubicles because the rooms are located in watertight cubicles. The system design basis is for a maximum unisolatable leak into the auxiliary building crescent room of 50 gpm.

Each of the manually operated SPPS subsystems consists of two crescent room sumps each with two 100% capacity pumps.

In the event one subsystem becomes inoperable, a functional test of the operable subsystem is performed in lieu of a full (92' day) surveillance test because of the difficulty in performing the full test and the pumps are used in normal plant operation.

This will provide the plant staff additional awareness of the systems condition.

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RIVER BEND - UNIT 1 B 3/4 5-3 Amendment No.38

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