ML20003H518

From kanterella
Jump to navigation Jump to search
Responds to IE Bulletin 80-25, Operating Problems W/Target Rock Safety-Relief Valves at Bwrs. All Target Rock Valves Modified from Three Stage to Two Stage During 1980 Refueling Outage
ML20003H518
Person / Time
Site: Pilgrim
Issue date: 04/08/1981
From: Morisi A
BOSTON EDISON CO.
To: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
81-72, IEB-80-25, NUDOCS 8105060257
Download: ML20003H518 (5)


Text

Tsc BOETON EDIRON COMPANY OENER AL OFFICES 8 00 SovLsTO N STR EET s o mTO N. M AB B ACH US ETTs 0219 9 A. V. M O RI S S MANAGER NUCLEAR OPE RATIONS SUPPO RT DEPARTM ENT April 8,1981 N

BECo. Ltr. #81-72 o

k(%

S r,

s fl

'y Mr. Boyce H. Grier, Director p-Office of Inspection and Enforcement Z MAY 0 419815-U fu lear Regulatory Commission

  1. EdlEY" 631 Park Avenue f

King of Prussia, PA.

19406

'b.,

License No. DPR-35 Dociet No. 50-293 Response to IE Bulletin No. 80-25

Reference:

A) IE Bulletin No. 80-25 " Operating Problems with Target Rock Safety /

Relief Valves at BWR's dated December 19, 1980

Dear Sir:

In Reference A) you specified actions to be taken by BWR Licensees. Bos ton Edison Company herein provides its responses to each of the required actions.

Item No. 1 If your facility has not yet installed or changed or is presently in the process of changing to the two-stage S/R valves, initiate appropriate quality control procedures to assure inspection of the solenoid actuators for excess Loc-tite prior to operation.

If the solenoid actuator manufactured by Target Rock Corporation is already installed in your facility, confirm its operability either by its operational performance (i.e., it has functioned as designed following an aging period of about 3 months in the higher temperature environment of power operating conditions) or by functional testing at full pressure during the next refueling shutdown of the facility.

Include in your report the results of all attempts to operate the two-stage S/R valve (s).

Respons'e to Item No. 1 Boston Edison Company has modified all four (4) Target Rock Safety / Relief (S/R) valves at Pilgrim Station from the three stage S/R valves to the two stage S/R valves during the 1980 Refueling Outage which ended on May 19, 1980.

i Relief valves 203-3B and 203-3C were tested at full pressure on August 1,1980.

Relief valve 203-3C was operated satisfactorily during a reactor scram on Nov-eder 1, 1980.

These valves had been subjected to the higher temperature environ-rent of power operating conditions since May 19, 1980 and therefore require no further testing.

I 810506035]

,805,TCN EDISON COMPANY Mr. Boyce H. Grier March 19,1981 Page 2 Relief valves 203-3A and 203-3D required solenoid assembly changes since their initial installation during November,1980.

These valves were functionally tested at full pressure,, prior to commencing a scheduled outage on February 28, 1981 Item No. 2 In the event that a S/R valve, recardless of make or model (e.a., both two or three stage), fails to function as designed, excepting for pressure setpoint requirements, and the cause of the malfunction is not clearly determined, under-stood, and therefore corrected, standard operation procedures shall require that the entire valve be removed from service, disassembled, inspected, adjusted, and pressure setpoint tested with steam for proper operation prior to returning the valve to service.

These overhaul requirements shall be at least equivalent to those applicable to periodic surveillance rehabilitation requirements. Appropriate revisions to your operating procedures shall be made to include these requirements.

Response to Item No. 2 Pilgrim Nuclear Power Station Operating Procedur.e No. 3.M.4-6 " Test, Disassembly Inspection and Reassembly of Main Steam Relief Valves" was revised to include these requi rements.

Item No. 3 A review of your S/R valve pneumatic supply systems shall be performed to deter-mine the potential for and magnitude of an overpressure condition.

The deter-mined overpressure potential of the pneumatic supply shall be compared with the maximum operating pressure capabilities of the solenoid actuator valves serving the S/R valves, so as to determine whether suoply pressure could result in valve malf unction.

Protective devices (such as relief valves) shall be installed in the proxim-ity of the S/R valves and set to protect against supoly pressure in excess of the operating pressure capabilities of the solenoid actuator device.

In addition, consideration should be given to modification or replacement to reduce the sensitivity of the solenoid actuator to pneumatic suonly overpressure.

Further, the failure, either high or low, of the pneumatic supply system shall be annunciated to"the control room operator.

The annunciated suoply pressure should be measured at a location as close as practical to the S/R valves and downstream of any check valve connecting two or more pneumatic scurces. Appropriate operating procedures shall be provided to guide operater response to such an occurrence of high or low supply pressure.

Response to Item No. 3 A short term review of the safety relief valve pneumatic supply system (Nitrogen /

Instrument Air System, P&ID M-220, 227) has been completed with the folicwing res ul ts.

PDCR 80-65 has been approved and a relief valve installed in the portion of the Nitrogen / Instrument Air System that supplies U2 to the safety relief valve actuators, PDCR 80-T-5 has been approved and a pressure switch and control roon

80sTaa, Eos ON COMPANY hr. Boyce H. Grier hirch 19,1981 Nge 3 annunciated alann installed which will actuate on high and low Nitrogen pressure to the safety miief valves.

Testing programs are being developed for all installed 6'lui pment.

A long term review of ti$e Nitrogen / Instrument Air System has been initiated by our Nuclear Engineering Department. This review addresses three areas:

1.

tiodi fication of the system to provide better pres. cure and flow control capabilities.

2.

Determin-ation of minimurn and maximtsn system operating pressures for all plant systams utilizing Np of instrument air.

3.

Development of an operating procedure in the event of high or low supply pressure.

A schedule will be provided for implementations of any resultant modifications identified during the review.

We trust that this information is responsive to your needs.

Should you have any questions or require any additional information, please do not hesitate to contact us.

Very truly yours, Attachments Commonwealth of Massachusetts)

County of Suffolk

)

Then personally appeared before me A. Victor Morisi, who, being duly sworn, did state that he is Manager - Nuclear Operations Support of Bosten Edison Company, the applicant herein, and that he is duly authorized to execute and file the submittal contained herein in the-name and on behalf of Boston Edison Company and that the statements in said submittal are true to the best of his knowledge and belief.

My Conmission expires: h.~./7,17/d

)kw w (M. b Om _

Notary Public cc:

Di rector, Office of Inspection & Enforcement Division of Reactor Construction Inspection U.S. Nuclear Regulatory Commission Washington, D. C.

20555

.t l =

}'

Attachment A to BECo Letter No. 81-Safety / Relief Valve Challenge Chc11enge Date S/RV #

Reason for Challenge Remarks 5/17/80 RV203-3A Performed tech spec surveillance All valves tested OK 3B Testing 3C 3D

}/25/80 RV203-3D Perform oper test per temp.

Valve failed to open Procedure TP 80-65 7/25/80 RV203-3D Test after inspection Valve would not open 7/25/80 RV203-3D Test after inspection Va3ve would not open 7/25/80 RV203-3C Perform oper test per temp. procedure Tested OK TP S0-65 7/25/80 RV203-3B Perforn oper test per temp. procedure Tested OK TP 80-55 7/26/80 RV203-3A Test after maintenan,ce related to Tested OK problems with RV203-3D 7/26/80 RV203-3D Test after maintenance Would not open 7/26/80 RV203-3D Test after maintenance Tested OK 7/26/80 Rv203-3D Retest (reliability)

Tested OK 8/1/80,

RV203-3A operability Test Tested OK 8/1/80 RV203-3B operability Test Tested OK 8/1/80 RV201-3C Operability Test Tested OK 8/1/80 RV203-3D Operability Test challenged 4 times Valve did not c r er.

8/3/80 RV203-3D Operability Test after maintenance Tesced OK 8/5/80 RV203-3D Operability test 8 times Test OK S ti es

. Challenge Date S/RV#

Reason for Challente Remarks 8/30/80 RV203-3D Aceelerated test program Tested OK 10/1/80 RV203-3D Rx scram / operator open & closed valve Valve opened - would via control switch not close 10/1/80 RV203-3C Rx scram / operator open & closed valve Operated satis:actori2y via control switch 10/5/80 RV203-3D Test after maintenance Tested OK 10/7/S0 RV203-3A Valve opened due to hi instrument s

nitrogen pressure to the RV solenoid 10/S/80 RV203-3A Test after maintenance Tested OK 10/31/80 RV203-3A Valve opened due to hi instrument nitrogen pressure to the RV solenoid M

5-f i

~

l

- -