ML18153B754

LER 89-015-00:on 890505,discovered That Setpoints Required for Auto Start of Fire Pumps Do Not Correspond to Tech Spec Requirements.Caused by Misinterpreted Tech Spec Surveillance Requirements.Pump Start Setpoints changed.W/890602 Ltr

ML18153B754
Person / Time
Site:	Surry
Issue date:	06/02/1989
From:	Kansler M VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
89-017, 89-17, LER-89-015, LER-89-15, NUDOCS 8906090270
Download: ML18153B754 (4)

Text

VIRGINIA ELECTRIC ANO POWER COMPANY Surry , _ , Station P. 0. Boa 315 Surry, Virginia 23883 June 02, 1989 U.S. Nuclear Regulatory Commission. Serial No.: 89-017 Document Control Desk Docket No.: 50-280 016 Phillips Building 50-281 Washington, D.C. 20555 License No.: DPR-32 DPR-37 Gentlemen:

Pursuant to Surry Power Station Technical Specifications, Virginia Electric and Power Company hereby submits the following Licensee Eve~t Report for Units 1 & 2.

REPORT NUMBER

• 89-015-00 This report has been reviewed by the Station Nuclear Safety and Operating Committee and will be reviewed by Safety Evaluation and Control.

Very truly yours, Station.Manager.

Enclosure cc: Regional Administrator Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30323 8906090270 890602 PDR ADOCK O~OOO?RO

-*- - -i=*oc: -

NRC Form 366 U.S. NUCLEAR REGULATORY COMMISSION (9-83)

APPROVED OM a NO. 3160-0104 LICENSEE EVENT REPORT (LER) EXPIRES: 8/31/88 FACILITY NAME (1) DOCKET NUMBER (21 I PAGE (31 TITLE (4)

Surry Power Station, Units 1 and 2 Io I 5 Io Io Io 12 1 810 1 loF OI 3 Setpoints Required for Auto Start of Fire Pumps Do Not Correspond to T,S, Requirements EVENT DATE (5) LER NUMBER (61 REPORT DATE (7) OTHER FACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR  :::::::::: SEQUENTIAL(::::::::: REVISION MONTH DAY YEAR FACILITY NAMES DOCKET NUMBER(S)

NUMBER ~

::::::::: NUMBER o I s oIs 8 9 8 I9 - o11 1s - o10 oI6 o12 8 I9 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Chock ono or moro of tho follo~ing/ (11)

MODE (9)

I 20.402(b)

- 20.405(c) 60.73(a)(2)(iv) 73.71(b)

POWER 20.406(a)(1 )(i) 60.36(c)(1) 60.73(a)(2)(v) 73.71 (c)

LEVEL - >--

1101 I 1 20.40s1.11111;;1 50.36(c)(2) 60.73(o)(2)(vii) OTHER (Spocify in Abstract

>-- below and in Texr, NRC Form 20.406(el(1 lliii) X 50.73(a) (2)(i) 60.73(1)(2)(viiil(A) 366A) 20.406(al(1)llv) 20,406(*)(1 )(vi - 60,73(a)(2)(ii) 50.73(e)(2lliiil 60,73(a)(2)(viii)(B) 60.73lall2ll*I LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER AREA CODE M.' R. Kansler, Station Manager 8 IO I 4 3 15 I 7 I - 13 I i l 8 14 COMPLETE ONE LINE FOR EACf; COMPONENT FAILURE DESCRIBED IN THIS REPORT (131 MANUFAC- REPORTABLE :.:.:::::*: ., .. ,.,  ::::--\::  :,:::

CAUSE SYSTEM COMPONENT MANUFAC-TURER TO NPRDS ): .... CAUSE SYSTEM COMPONENT TURER I I I I I I I .*.:. ..... I I I I I I I

... ,.*..*.-;.: *:*::*.- *.*:*:-::*.*

,:.;.:::::::::::::::::::,:,::,...;*:*:*:*:*:*:*:*

I I I I I I I *.*.*..*.-;.: .,. .*.*.:.: ,....,.

I I I I I *1 I *:-::*:*:*:*:*:-:.;.;.:: *:*:*:*:*:*:*:*:*

SUPPLEMENTAL REPORT EXPECTED (14) MONTH DAY YEAR EXPECTED I YES /If yes, comploto EXPECTED SUBMISSION DATE/

ABSTRACT (Limit to 1400 spacss, i.e., approximately fifteen single-space typewritten lines) (16) bl NO SUBMISSION DATE (15)

I I I On May 5, 1989 during a review of a change request for a fire protection system surveillance test, it was noted that the setpoints required for the automatic starts of the fire protection pumps did not appear to correspond to the requirements in Surry's Technical Specifications (T.S.).

The motor driven and diesel driven fire pumps' autostart setpoints are 90 + 4 psig and 80 + 4 psig, respectively.

However, T.S. 4.Y8.B.l.f(3) requires the pumps to maintain system pressure equal to or greater than 90 psig.

Therefore, the diesel pump would technically be considered inoperable and the motor driven pump would be inoperable if the setpoint drifted below 90 psig. Operability of the fire protection pumps is required by T.S. 3.21.A.2.a. An engineering evaluation will be performed to change the pumps' start setpoints to 80 psig and a T.S. change will be submitted. In the interim, the fire pump automatic start setpoints have been changed to comply with Technical Specifications. The applicable Periodic Test will be revised accordingly.

NRC Form 366 19*831

NRC 1-orm . .A U.S. NUCLEAR REGULATORY COMMISSION 111-831 LICENSEE E - T REPORT (LERI TEXT CONTINUA-N APPROVED 0MB NO 3150-01Gc EXPIRES: 8/31/8.<

FACILITY NAME 111 DOCKET NUMBER 12:

I LER NUMBER 16*

• ,*-:***tSEOUENTIAL *.*.*IRE VIS ID""

PAGE 13 YEAR NUM!!!IE R ***lNUM!ER I

TEXT Ill Surry Power Station, Units 1 and 2 mon, .-ce o -

• u* - - NRC form 3li6.A '*11171 8I 9 - 0 I (I 5 -1 0 I O O i 2 I° F O 13 1.0 Description of the Event On May 5, 1989 during a review of a change request for a fire protection system (EIIS-KP) surveillance test, it was noted that the setpoints required for the automatic starts of the fire protection pumps (EIIS-P) did not appear to correspond to the requirements in Surry's Technical Specifications. The surveillance requirements in T.S. 4.18.B.l.f(3) states that "the fire suppression water system shall be demonstrated operable at least once per 18 months by verifying that each high pressure pump starts (sequentially) to maintain the fire suppression water system pressure equal to or greater than 90 psig". Contrary to this requirement, the automatic setpoints for the motor driven and diesel driven fire pumps are 90 + 4 psig and 80 + 4 psig, respectively. Failure of the fire pumps to meet their performance requirement as specified in T.S. Section 4 surveillance requirements would technically render the pumps inoperable per the T.S. definition of operability. Operability of the fire protection pumps is required by T.S. 3.21.A.2.a.

2.0 Safety Consequences and Implications The fire water system is maintained at a static pressure of 100 to 110 psig by a maintenance pump and a hydropneumatic. tank. A motor driven pump and a diesel driven pump, each with a capacity of 2500 gpm at a dynamic head of 231 feet, are provided to supply fire water for the plant's fire suppression system upon demand. Either of these pumps can provide the required flow to maintain system pressure at greater than 90 psig to ensure operability of the system. An automatic start of the motor driven fire pump would occur when fire water demand decreased system pressure to less than 90 psig. Should the motor driven pump fail to start, the diesel driven pump would automatically start at a pressure of 80 psig. The additional time required for the automatic start of the diesel pump, due to the lower start setpoint, would be insignificant and would have no effect on the operability of the fire suppression system.

Therefore, the health and safety of the public were not affected.

NRC FORM 366.t. .:.,; * . j ~ ti C' - * * - :,r- ,, \*(

19-83,

NRC rorm . .A U.S. NUCLEAR REGULATORY COMMISSION 19-831 LICENSEE EV.T REPORT (LERI TEXT CONTINUAT- APPROVED 0MB NO 31 50--0lC'C EXPIRES: 8/31/8!<

FACILITY NAME 11 I DOCKET NUMBER 121 LEA NUMBER 16, I PAGE IJ

. *.-:***ISEOUENTIAL * *'IREVISIO ....

Jo,l YEAR NUM(IIECI ** NUM!IER Surry Power Station, Units 1 and 2 TEXT fll_mor._,. _ _ .,.. -NRCk>nn.l15&111'*11171 o 1s101o10J2 J8IO 819 -o 11 Is - oI o 0 i 13 3.0 Cause In 1984, the Technical Specification surveillance requirements were reviewed to verify that procedures existed to ensure compliance with the Technical Specifications. At the time of the review, the T.S.

was interpreted to mean that the pumps would be required to start sequentially but not necessarily at a pressure greater than 90 psig since the system pressure would be maintained at 90 psig after the pumps started. Since Periodic Tests existed to assure this performance, the requirements were considered to be met. In addition, the Updated Final Safety Analysis Report, Section 9.10.2.2., states that the motor driven fire pump would automatically start when system pressure drops below 90 psig, and the diesel driven pump would start if the system pressure continued to drop. It is assumed this information was used as a basis for establishing the original start setpoints.

4.0 Immediate Corrective Action(s)

An Engineering Work Request was initiated to evaluate changing the fire pump automatic start setpoints.

5.0 Additional Corrective Action(s)

An engineering evaluation has been performed to justify changing the required pump start setpoints to greater than or equal to 80 psig and a T.S. change request will be submitted. In the interim; the fire pump automatic start setpoints have been changed to 95

+ 4, -0 psig and 90 + 4, -0 psig for the motbr driven and diesel driven pumps, respectively. The applicable Periodic Tests will be revised accordingly.

6.0 Action(s) Taken to Prevent Recurrence None required.

7.0 Similar Events N/A 8.0 Manufacturer/Model Number(s)

N/A

• * , .", , -

• I ., I'\ t' * - * ' * :"I I"~* \I(

NRC FORM 386.A 19-BJ,