ML19249E446

LER 79-075/01T-0:790907,w/reactor Critical,Rhr Svc Water Pumps A-D Would Not Pump Rated Flow at Rated Discharge Pressure.Caused by Incorrected Formulas for Calculated Inlet & Discharge Pressures.Pumps Retested

ML19249E446
Person / Time
Site:	Hatch
Issue date:	09/18/1979
From:	Coggin C GEORGIA POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19249E445	List: ML19249E444 ML19249E446
References
LER-79-075-01T, LER-79-75-1T, NUDOCS 7910010425
Download: ML19249E446 (3)

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io i2 l_1li_th._the Unil Lrealtor_ critic _al at_2304_mc90wltts__thermLp_ owe.t,_i t was disccvered "A", "C" and "D" would not nump_ rated flow at rated I

101: 1 I that the RHR service water pumps and Rated I f o la I di_scharce orcSlur_e_as_p_er HNP- 1-3167. "P&_S_crv_i ce__'sta ter Pugp Goerabi_l i ty tesL__Later, the__"B" pu p was also diacnosed to have the same urablem.

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oB 1 thn_2hLscryice veier svuercnvid_ncLEe_armen_eperahle, the reactor was taken to The other crieroency core coolina f o 171 L.co1Lshat1! cures oer the Ter3_Snec_s_section 3. 5.C.

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J l tect encineer was consulted about the ecuations, their succestions were then iralem-j is- I ented in e revision to HNP-1-3167 and a Document Chance to the Tech Snecs lim (continued)  !

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Georgia Power Company

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s Caxley, Georgia 31513 JL s

.f;f Event Description and Probable Consequences (continued) operability test is a repetitive occur :nce for the RHR service water pumps; reference License Event Report No. 50-321/1979-063.

Cause Description and Corrective Actions (continued)

The pumps were then successfully retested. The Unit 1 & 2 plant service water, RHR service water and standby plant service water pump procedures were all reviewed and found to contain the same formulas as mentioned before.

All the procedures were revised prior to Unit startups. A further review of the procedure formulas revealed that the original " Delta P" formula was cor-

- rect, only the required RHR service water pump Total Dynamic Head in feet needed to be changed.

1060 010 W

SUPPLEMENT TO LER 50 7?1/1970-075 1

On September 7, 1979, with the reactor critical at 2304 megawatts, while performing the RHR service water pump operability procedure (HNP-1-3167), RHR sortice water pumps E11-C001A, C, and D would not pump rated flow (4000 GPMT a t, rated pressure as required by H"P-1-3167 and Tech. .3 0 e c .

section 4.5.C.1.b. The 1E11-C001A pump had a flou of '! O / '4 GPM at 35S DSIG; the 1E11-C001C p u rr n had a flow of 4024 GPV at 179 PSIG, and the 1E11-C001D pump had a flow of h024 G P at 173 PSIG.

After the discharge pressu"e gages /1E11-R00hA-Di were recalibrated, it was d e t e r". i n e d that 1E11-C0014 had a:so failed to meet the flow and pressure requi-e v nts; the p u r. ?

had a flow of 4156 GPM at 405 PSIG. At this time the "eactor was brought to cold shutdown as per Tech. Spec. sect!on 0.5.r.

Due to the inherent problem of the ptmps failing to p u r.o rated flow at rated pressure when the river water level is low, engineering services was consulted to review the pump pressure formulas in HNP-1-3167. The initial review i nd i c a '.e d that the

. formulas for inlet pressure, discharge pressure, and differential pressure were incorrect. The A"chitect 7.n rz i n e e r s submitted neu formulas which were incornorated into the Unit 1 and 2 operability procedures for RHR service water olant service water, and the standby plant service water ounns.

On 9-9 74, the Unit 1 RHR service water oumos we c "etested using the new formulas clus the corrected " Total P/nanic Headd

• for the pumos granted by the Tech Soecs c h a n :* e . s.11 the nu .o s passed their operability test so new reference data was taken and the Unit started up. .

A later review of the new roanulas revealed that the original differential pressure formula was correct. Thus, the original

" Delta P" formulas were reinserted i n t.o their respective operabisity procedures.

As far as the RHR service water procedure is concerned the valves derived from the new " Delta P" formula are very close (within a few PSI) and in a conse"vative direction to those valves derived from the old " Delta P" fornula with the new total dynamic head valve. The "eason the old formula was reinserted is because the new formula did not take into

. account the Hydraulic Institute Standards for t. h e pumps.

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o pJ d i) 1060 011

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