ML20070J865

Forwards 120-day Response to Generic Ltr 89-10,Suppl 3, Consideration of Results of NRC-Sponsored Tests of Motor-Operated Valves. Criteria to Determine If Deficiencies Exist in HPCI or RCIC Valves Listed on Encl

ML20070J865
Person / Time
Site:	Browns Ferry
Issue date:	03/13/1991
From:	Burzynski M TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-89-10, NUDOCS 9103180181
Download: ML20070J865 (6)

Text

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MAR 131991

.U.S. Nuclear Regulatory Commission

-ATTW: Document Control Desh Washington, D.C. 20555 Gentlement

In-the Matter of ) Docket Nos. 50-259 Tennessee Valley Authority ) 50-260 50-296 BROWNS -z FERRY NUCLEAR PLANT-(UFN) - RESPONSE TO GENERIC: LETTER (GL) 89-10

--SUPPLEMENT 3. " CONSIDERATION OF THE RESULTS OF NRC-SPONSORED TESTS OF MOTOR-OPERATE 0 VALVES" (MOV) l

Reference:

Letter from E...G. Wallace to NRC dated December 10, 1990,.

" Browns Ferry Nuclear Plant (BFN) - Response to Generic-Letter (GL) 89-10, Supplete.ent 3 ' Consideration of the <

Results of NRC-Sponsored. Testa of Motor-Operated Valves' 4

(MOV) **

The purpose of this --letter is to provide the required 120-day response specified in.GL 89-10, Supplement 3. GL.89-10, Supplement 3 was; received .

-onsite on November 13 -1990. This response delineates criteria used-to determine whether. deficiencies exist- in the pritnary contdument isolation-MOVs for the High Pressure Coolant Injection and Reactor Core-Isolation Cooling steam supply lines and the Reactor: Water Cleanup wat,er supply  !

line.

BFN stated in the above reference-that a plant specific Safety Assessment

- for the subject MOVs was available onsite for NRC staff review. This Safety Assessment was developed in part utilizing-the criteria described-

- below.

1. Comparison of the Idaho National Engineering Laboratory test results for similar valves under similar conditions.

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2. Comparison of current thrust requirements with actual thrust developed.

-3. . Comparison of operator capability at design basis conditions.

4. Review of operating experience.  ;

In performing this evaluation. TVA has not-identified any deficiencien  !

-for the_ subject MOVs at BFN. [-

-The enclosure to this letter providou a detailed explanation of the.

= criteria used and the manner in which it was applied. Table 1 of the enclosure sumarizes comparisons performed on the subject MOVc.

Units 1 and 3 remain in an extended outage and'therefore comparisons for the subject MOVs-in these units were not performed. Generic Letter 89-10 will be implemented prior to the restart of each of these units.

No new commitments are made in this letter. If you have any questions on lthis matter please-telephono patrick p. Carier at (205) 729-3566.

Very truly-yours.

TENNESSEE VALLEY AUTHORITY Mark J ,3urzyn , Manager Licensing Projects ;

Subscribed-andagorn.tobeforp-mm on this. /3L dayof[/]dML 1991 Notary Public.

M My Commission Expires // '/ 9S Enclosure cet- -(See page 3) l'

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. 33 MAR 131991- ,

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U.S. Nuclear' Regulatory Commission:

i ce1(Enclosure): t

=Ms. S.ic.~~ Black, Deputy Director'

-Project Directorate 11-4 U.S. Nuclear Regulatory Commission.

One White Flint, North-

11555 Rockville Pike,-

Rockville', Maryland 20852 NRC Resident Inspector Browns Ferry Nuclear Plant >

Route 12, Box 637:

Athens, Alabama--35609-2000

_Mr. Thierry M. Ross,-Project Manager

-U.S. Nuclear Re5ulatory Commission One White Filnt, North 11555.Rockville Pike

,Rockville, Maryland 20852 e

Mr.: B. A. Wilson, Project Chief U.S. Nuclear ReBulatory.Commisolon- t Region =II; .

101 Marietta Street, NW, Sutto 2900 }

Atlanta, Georgia- 30323; ,

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ENCLOSURE GENERIC LETTER 89 'O SUPPLEMENT 3 - 120 DAY RESPONSE The following criteria were used to determine if any deficiencies exist in the High Pressure Coolant Injection (HPCI) Reactor Core Isolation Cooling (RCIC),

and Reactor Water Cleanup-(RWCU) Primary Containment Isolation valves at BFN.

The-criteria utilized were:

1. Comparison of the Idaho National Engineering Laboratory (INEL) test results with BFNs current thrust requirements for similar valves undet similar conditions. .This evaluation compared valves of the same size.

type, operating conditions and manuf acturer (if same as valves tested) that are used at BFN (i.e. operating pressure / maximum dif ferential pressure of 1000 psi). The results of this compar3 son confirmed that the current thrust requirements for the valves at BFN are consistent with the applicable INEL test results.

2. Comparison of the current thrust requirements with actual thrust developed at the torque switch trip based on diagnostic test results.

This comparison confirmed that there is available margin between the thrust required and thrust developed at torque switch trip to compensate for unexpected seating forces that may develop. ;The torque switches on these valves are bypasased for 97% of the closing stroke and therefore only the seating portion of the closing stroke is controlled by the torque switch.

3. Comparison of operator capability at design basis con 31tions (i.e.

degraded voltage and elevated ambient temperatures) with the

• requirements and thrust developed at torque switch trip. Using standard Limitorque sizing equations for the particular operator configuration, this comparison confirmed that there is sufficient margin above the calculated thrust requirement to ensure that the valve operator can overcome any unexpected forces which may occur during 97% of the closing valve stroke. Also, thia confirms that the valve operator is-capable of--

achieving torque switch trip at design basis conditions during the last 3% of the closing stroke.

4. . Review of BEN's operating experience to determine if any operational problems had been encountered with the closure of these valves under flow / differential pressure conditions. This review revealed no adverse conditions regarding the operation of these valves or their ability to function under normal condition.

CONCLUSION:-

Comparisons 1 through 3 are shown in Table 1 and confirm that_the valve operators and torque switch settings for these valves are adequate to perform their design basis functions. It should be noted that each subject system is-equipped with its own individual primary containmer.t. isolation group. That particular group's initiation signal will cause closure of_the isolation valves for that system. A review of operating histories has shown-that BFN has not experienced operational problems with the subject valves. Based on the above comparisons BFN has not identified any deficiencies on the subject MOVs requiring' corrective action.

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TELE 1 .  :

COMMIS0NOfBfNUNIT2H0VSWITHINELTESTRESUI.TS INEL TEST BFN THRUST AT OPERATOR RESULTS' THRUST' TOROUE CAPABILITY

• SYSTEH FUNCTION UNID (LBS) (LBS) SWITCH (LBS)

TRIP'(LBS)

RWCU INBD ISOL 2-FCV-69-01 14,000 14.019 19.067 31.124 RWCU OUTBD ISOL 2-FCV-69-02 14,000 14,019 23,073 27,020 RCIC In8D ISOL 2-FCV-71-02 N/A 4,600 7,683 8.954 RCIC OUTBD ISOL 2-FCV-71-03 N/A 4.600 5.350 12.480 HPCI INBD ISOL 2-FCV-73-02 29,000 47,311 55.416- 72,537 HPCI 'OulBD ISOL 2-FCV-73-03 29,000 37,849 52,600 56,935

' Correlations to the INEL test results as published in Information Notice 90-40 are based on valve type, size and manufacturer. INEL tested 6" flex-wedge gate valves manuf actured by Velan similar to the RWCU valves used at BFN.

The correlation to the HPCI valves is loosely based on 10" Powell valves tested versus 10" Crane-Chapman valves used at BFN which have similar construction. INEL did not test any 3" valves, so comparison with the RCIC valves at BFN could not be made.

• These are the current thrust requirements based on the manufacturer's thrust calculations. The thrust value for 2-FCV-73-02 was a result of higher seating thrust required due to LLRI leakage requirements.

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The thrusts shown are based on static diagnostic test results at torque switch trip and ensure that the required micir:um thrust is met.

Operator capability is calculated using standard Limitorque sizing methodology and considers degraded voltage to the operator.

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