ML18025B906

Corrections to 821015 Proposed Changes to Tech Spec 179 Re Values of Flow for Surveillance Testing of LPCI

ML18025B906
Person / Time
Site:	Browns Ferry
Issue date:	01/07/1983
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18025B905	List: ML18025B904 ML18025B906
References
NUDOCS 8301170502
Download: ML18025B906 (8)

Text

ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION REVISION TVA BFNP TS 179 SUPPLEMENT 3 BROMNS FERRY NUCLEAR PLANT UNIT 2 830ii70502 830i07 t PDR ADOCK 05000260 PDR

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS

3. 5. B. Re i He R a

'.B. Re Be Rom l 4

Containment i Coo I ng )

Containment Cooliag)

1. The RBRS shall be

l. a. Simula ted Once/

oper abl o: Autoinatic Opasatiag (1) prior to a hctuatioa Cycl e reactor startup Teat fsom a Cold Opera-Condition; or b. Pump Once/

bil i ty month (2) when there is c. Motor Opera- Once/

isradiated fuel tod valve month in thc reactor vessel and when operability the seactor Flow Once/3 vessel prcssure d. Pump Rate months is greater than atmospheric, a. Testable Once/

exoept as check valve 'perating specified in cycl e speoifioatioas 3.S.B.2, through Each LPCI pump shall dal iver 3.5.8.7 9,000 gpm against aa indicated system pressure of 125 psig. Two LPCI pumps in the same loop shall

2. With the reactor vessel pressure less deliver 12 ppp gpm against an than 105 psig, the indicated system pressure of RBR may ba removed ogp psigo from service (except that two RHR pumps- 2. An air test on the drywall and torus containmant cooling headers and noxxles shall be mode and associated conducted once/S years. h hoat oxchangars must water test may be performed on remain oparabla) for the torus header in lieu of thc a period not to ais test.

exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> while being drained of suppression chambes quality water and filled with primary cool'ant quality rater provided that during cooldown two loops with one pump per loop or ono loop with two pumps, and associated diesel 145

4 L,

ENCLOSURE 2 DESCRIPTION AND JUSTIFICATION (TVA BFNP TS 179 SUPPLEMENT 3)

By letter from L. M. Mills to H. R. Denton (NRC), dated October 15, 1082 (TVA BFNP TS 179), we submitted proposed chanpes to Technical Specification 4.5.8.1 LPCI pump surveillance conditions to consider installation of a flow restricting orifice. The values of pump flow proposed in that submittal wer e based upon an incorrect valving configuration. The technical specification surveillance values in this

'proposed change ( 12,000 gpm, 250 psig) reflect the correct valving configuration for LPCI surveillance testing.

The proposed changes of Supplement 3 relate only to the method in which the surveillance test for LPCI pumps operability is performed and has no adverse impact on the LPCI or containment cooling modes of RHR operation.

These changes, therefore, do not affect the results of the safety evaluation as presented in the October 15, 1982 submittal (TS 179).

ENCLOSURE 3 CONTAINMENT COOLING ANALYSIS WITH 13,000 GPM LOW PRESSURE COOLANT INJECTION FLOW BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 The performance of the RHR heat exchangers and the primary containment response for the Design Basis Accident with two RHR pumps in one loop and total flow of 13,000 gpm were analyzed. The analysis was performed by General Electrio Company using the following initial conditions and assumptions:

1. Reactor operation at 105 percent of rated steam flow (3440 MWT).

2. Service water and initial pool temperature of 95 F.

3. May-Witt decay heat.

4. Two heat exchanger's and two RHR pumps (single 1oop) on at 10 minutes.

5.'otal RHR flow of 13,000 gpm.

6. K factor of 223.8 Btu/sec F per heat exchanger.

This resulted in a maximum bulk pool temperature of 177.8 F at approxi-mately 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. The containment response is shown in the attached figure of drywell and wetwell temperature versus time.

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