ML20126F573

Provides Correction of Correspondence to NRC for Emergency Feedwater Sys at Plant

ML20126F573
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/22/1992
From:	Alexion T, Bevan R Office of Nuclear Reactor Regulation
To:	Yelverton J ENTERGY OPERATIONS, INC.
References
TAC-M84014, NUDOCS 9212300407
Download: ML20126F573 (4)

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UNITED STATES 8"

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December 22, 1992 Docket Nos.

50-313 and 50-368 Mr. Jerry W. Yelverton Vice President, Operations ANO Entergy Operations, Inc.

Route 3 Box 137G Russellville, Arkansas 72801

SUBJECT:

CORRECTION OF CORRESPONDENCE TO NRC FOR THE EMERGENCY FEEDWATER SYSTEM AT ARKANSAS NUCLEAR ONE, UNITS 1 & 2 (ANO-l&2) (TAC N05.

M84014 AND M84015)

In an effort to clarify and correct your January 31, 1980, response (regarding the ANO-2 emergency feedwater (EFW) system) to the recommendations of NRC letter dated November 6, 1992, Entergy Operations, Inc. (the licensee) provided additional information by letter dated June 19, 1992.

The recommendations involved are Short Term Recommendation GS-6 and Additional Short Term Recommendation 4 (AST-4).

GS-6 recommended that licensees propose Technical Specification (TS) changes to assure that prior to plant startup following an extended cold shutdown, a flow test would be performed to verify the normal flow path from the primary auxiliary feedwater (AFW) water supply to the steam generators.

The flow test was to be conducted with the AFW system valves in-their normal configuration.

Recommendation AST-4 recommended that licensees with plants which require local realignment of valves to conduct periodic tests on one AFW train, anA there is only one-train left for automatie operation, should propose TS changes to provide a dedicated individual stationed at the local valves. At the request of the control room, this individual would realign the AFW train from the test mode to the operational mode.

Recommendation GS-6 L

The underlying major concern associated with GS-6 was that some plants had AFW systems which contained local manual valves located inside the containment.

l Because these valves could not be routinely checked during normal plant operation, the staff was concerned that they might be inadvertently closed or left closed as a result of containment entries during an extended cold shutdown.

It was intended that at least one AFW flow path be assured by actual flow test to the steam generators prior to startup following an extended shutdown.

Normal periodic tests and valve alignment checks would be relied on for proper operation of the remaining train or trains. However, t

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9212300407 921222

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1Mr.< Jerry W._Yelverton:

1Entergy 0perations, Inc.

-Arkansas Nuclear One, Units 1 &:2-3

'CC:

Mr.. Donald C. Hintz, President Mr. John R.iMcGaha-and Chief Executive Officer Vice President,-Operations Support:

Entergy Operations, Inc.

Entergy Operations,:Inc.-

P. O. Box 31995 P. 0.-Box 31995 1

Jackson,_ Mississippi.39286 Jackson,. Mississippi 39286 Mr. Robert B.-McGbhee Mr. R. A. Fenech=

Wise, Carter, Child &-Caraway General Manager, Plant _0perations P. O. Box 651 Entergy Operations, Inc.

' Jackson; Mississippi -39205; Route 3 Box 137G

~

Russellville, Arkansas 72801 Mr. Charles B. Brinkman, Manager Washington Nuclear Operations ~.

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Mr. Nicholas S. Reynolds ABB Combustion Engineering Nuclear;Powerr Winston &--Strawn 12300-Twinbrook Parkway, Suite'330

1400 L' Street, N.W.

Rockville, Maryland > 20852 Washington,-D.C.

20005-3502 Mr. James-J.!fisicaro-Mr. Robert'B. Borsum Director, Licens_ing Licensing Representative.

Entergy Operations, Inc.

B&W Nuclear Technologies Route 3, Box'137G1 1700 Rockville Pike, Suite 525 -

Russellville,1 Arkansas -72801' Rockville, Maryland 20852 Admirali Kinnaird R. McKee, USN (Ret)

Senior Resident Inspector ~

214' South Morris Street-U.S. Nuclear Regulatory Commission Oxford,LMaryland-21654

-1 Nuclear Plant-Road

'Russellville, Arkansas 72801 Regional Administrator, RegionLIV--

U.S. Nuclear Regulatory: Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Honorable Joe W. Phillips County Judge of Pope County Pope County Courthouse-

- Russellville, Arkansas _ ~ 72801 L

Ms. Greta Dicus, Director Division of Radiation Control'and Emergency Management _

Arkansas' Department of Health.

'4815 West Markham Street Little Rock, Arkansas.72205-3867 g

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Mr. Jerry W. Yelverton,

1 most licenseas interpreted this recommendation to mean a flow test should be conducted on all AFW trains except any train that was used for a normal startup. The startup flow path would suffice to verify flow path availability for this train.

At ANO-2, TSs exist for the A train of emergency feedwater (EFW), but none for the B train, which was used for startup, but did not use its primary water source. The licensee has subsequently installed a third train of backup feedwater at ANO-2, the AFW pump, which is normally used for plant startup.

In addition, the B train is tested by procedures during each cold shutdown prior to heatup.

At ANO-1, prior to a plant startup following a refueling shutdown, a combination of EFW tests are performed that verify the normal flow path from the condensate storage tank (CST) to the steam generators.

The staff has reviewed the licensee's operation of the EFW system at both ANO-1 and ANO-2 and agrees with the licensee's conclusion that no further TSs are required to satisfy the recommendations of GS-6 because each train is tested and the major concern (manual valves inside containment) does not exist.

Recommendation AST-4 For ANO-2, the licensee's initial response to AST-4 was that local realignment of valves was not necessary to perform periodic tests of the EFW system.

However, subsequent review by the licensee determined that local realignment of valves was necessary to test the A train of the system. Currently, an operator is stationed at the local valves during A train testing.

The licensee has since changed the procedures for testing the B train of EFW to also require local realignment of valves during periodic testing.

However, procedures were not initially revised to require stationing an operator at the local valves during the tests. According to the licensee's submittal, the procedures for train B have now been revised to station an operator at the local valves during the tests. Also, a third train of backup feedwater, the AFW system, has been installed to supplement the EFW system at ANO-2.

At AN0-1, the licensee's reevaluation of the applicability of AST-4 confirmed that local realignment of local valves was not necessary to perform periodic testing of the EFW system trains. Therefore, Recommendation AST-4 is not applicable to ANO-1.

The staff has reviewed the licensee's operation of the EFW system with respect to AST-4 and agrees with their conclusinn that no further TSs are necessary.

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'Mr. Jerry W. Yelverton For ANO-2, this conc 1'usion is based on the procedural controls in place plus the added third train of AFW which provides another backup to the train in test.

For ANO-1, this recommendation is not applicable because no local realignment of valves takes place during periodic testing.

Sincerely, a

Roby B.

evan, Project Manager Project Directorate IV-1 Division of Reactor Projects - III/IV/V-i Office of Nuclear Reactor Regulation-C'

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()%isf Thomas W. Alexion, Project Man ~ager-Project Directorate IV-1 l

Division of Reactor Projacts - Ill/IV/V Office of Nuclear Reactor Regulation 4

cc:

See next page l

l 1

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jt Mr. Jerry W, Yelverton for ANO-2, this conclusion is based on-the procedural controls in place 'plus-the added third train of AFW which provides another backup to the train in test.

For ANO-1, this recommendation is not applicable because no local realignment of valves takes place during periodic-testing.

Sincerely, ORIGINAL SIGNED BY:

Roby B. Bevan, Project Manager-Project Directorate IV-I-Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation ORIGINAL SIGNED BY:

Thomas W. Alexion, Project Manager Project Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation cc:

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Docket File-NRC & LPDRs

-PDIV-1 r/f JRoe MVirgilio JLarkins PNoonan RBevan HRathbun TAlexion 0GC ACRS (10)

PDIV-1 p/f ABeach, RIV 0FC LA/PDIV-lb I/PDIV,I.o PM/BDtV T (

PM/PDIV D/PSFVi NAME PNoondn [I ' 'HRathbM TAlexfdTykiiBednb

[LIIehfs DATE-12/7/92 12/f/92 12/l$/92 12/ 2.f/92 12pb/92 0FFICIAL RECORD COPY Document Name: AR84014,COR 3

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