05000298/LER-1981-015-03, /03L-0:on 810531,twelve Penetrations Were Found Leaking Excessively.Ten Caused by Normal Wear & Two by Improper Limitorque Operation.Valve Repairs Performed

/03L-0:on 810531,twelve Penetrations Were Found Leaking Excessively.Ten Caused by Normal Wear & Two by Improper Limitorque Operation.Valve Repairs Performed

ML20009F049
Person / Time
Site:	Cooper
Issue date:	06/30/1981
From:	Marker D NEBRASKA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20009F045	List: 05000298/LER-1981-015, Forwards LER 81-015/03L-0.Detailed Event Analysis Also Submitted 05000298/LER-1981-015-03, /03L-0:on 810531,twelve Penetrations Were Found Leaking Excessively.Ten Caused by Normal Wear & Two by Improper Limitorque Operation.Valve Repairs Performed
References
LER-81-015-03L, LER-81-15-3L, NUDOCS 8107280631
Download: ML20009F049 (1)

LER-1981-015, /03L-0:on 810531,twelve Penetrations Were Found Leaking Excessively.Ten Caused by Normal Wear & Two by Improper Limitorque Operation.Valve Repairs Performed

Event date:
Report date:
2981981015R03 - NRC Website

text

-

t Mr. K. V. Seyfrit, Director June 30, 1981 Page 2.

Initial leakage was found to be.39 cfh. The established limit is 0.1 scfh. aCAD-1311 Limitorque motor operator was adjusted. After adjust-ment the leakage was reduced to.08 scfh. The leaking valves are Anchor 1" gate valves with Limitorque motor operators.

X-14 RWCU, Inlet to RWCU System.

RWCU-M0-15 (supply inboard isolation) and RWCU-MO-18 (supply outboard isolation).

Initial leakage was found to be 39.67 cfh. The established limit is 2.0 scfh.

RWCb-MO-15 and RWCU-MO-18 were disassembled and gates removed and lapped, seals cleaned and reassembled. After reassembly, the leakage check was 39.6 scfh. The leakage was determined to be from RWCU-M0-15.

3 ove the established limit, further repair b

Even though the leakage wat was not initiated because of the safety margin in the established limits.

Primary containment would be maintained by the outboard isolation valve.

RWCU-MO-15 and M0-18 are Anchor 6" gate valves.

i X-13A RHR Loop "A" Supply to RPV.

RRR-MO-25A (loop "A" inboard injection block) and RHR-M0-27A (1)op "A" outboard injection block).

Initial leakage was found to be 34.12 cfh. The established limit is 10 scfh. RHR-M0-25A was disassembled and the seats were lapped, seal rings replaced and reassembled. After repair of RHR-M0-25A, the leakage was 0 scfh.

RHR-M0-25A is an Anchor 24" gate valve.

X-8 Main Steam Line Drain. MS-MO-74 (inboard isolation valve) and MS-MO-77 (outboard isolation valve).

Initial leakage was found to be 18.28 cfh. The established limit is 1.5 scfh. MS-MO-74 was disassembled, the disc removed and lapped, the seats were cleaned, and valve reassembled. After repair, the leakage was.23 scfh. MS-M0-74 is an Anchor 3" gate valve.

X-205 ACAD Porge Supply Line to the Suppression Chamber. ACAD-1303MV (out-Soard isolation valve) and ACAD-1304MV (inboard isolation valve).

The initial leakage was too rapid to determine an initial leak rate.

The established Timit is.1 scfh. The gate was removed and lapped, the seats were cleaned, and the valve reassembled. Retest indicated ACAD-1303MV was not shutting tightly. A new Limitorque was installed cn *E valve. After replacement of the Limitorque, the leak rate was reJ"ceu to.007 scfh. ACAD-1304MV was not repaired or adjusted. Therefore, primary containment would have been maintained by the inboard isolation valve ACAD-1304MV. The leaking valve is an Anchor 1" gate valve with a Limitorque operator.

8107280631 810630 PDR ADOCK 05000290 S

PDR

• M*:. K. V. Ocy'rit, Director June 30,'1981 Page 3.

L-212 RCIC Turbine Exhaust to the Suppression Chamber, RCIC-15CV and RCIC 37.

Initial leakage was found to be 9.3 cfh. The established limit is 1.0 scfh. RCIC-37 was disassembled for repair and indicated rough seating surfaces. The seats were lapped and the disc cleaned and valve reas-sembled. After rep..ir to RCIC-37, the leakage rate was 2.3 scfh. Even though the leakage was above established limit, further repair was not initiated because of the safety margin in the established limits. RCIC-37 is an 8" Anchor globe valve.

X-210B and X-211B RHR to Suppression Pool.

RHR-M0-34B (supprassion pool cooling inboard)

RHR-M0-38B (suppression pool inboard spray) and RHR-M0-29B (suppression pool cooling and spray outboard block valve).

Initial leakage was found to be 210 cfh. The established limit is 8.0 scfh. RHR-M039B was disassembled, the seats and gate were lapped, and a new bonnet gasket installed.

rhe valve was reassembled and tested.

After repair of RHR-MO-39B, ne leakage was 1.68 cfh. RHR-HV-34B and RHR-MO-38B were not repaireo or adjusted. RHR-M0-39B is an Anchor 18" gate valve.

X-220 Primary Containment Purge and Vent Exhaust From Suppression Chamber.

PC-M0-230 (inboard isolation valve) PC-AO-245 (outboard isolation valve). PC-57MV (inboard isolation bypass) and ACAD-1308MV (ACAD torus vent).

The initial leakage was too u

termine an initial leak rate.

The established limit is 5.0 scfh.

FC-A0-245 was disassembled and the rubber seating ring replaced. After repair, the leakage was 2.8 scfh.

PC-230MV and PC-57MV were not repaired or adjusted. Therefore, primary contcinment would have been maintained by the inboard isolation valves.

PC-245AV is - 24" Allis-Chalmers butterfly valve.

X-221 1

RCIC Vacuum Pump Discharge to Suppression Chamber The test volume for this penetration is between RCIC-12CV and manual valve RCIC-42.

Initial leakage was found to be 2.23 cfh. The estab-i lished limit is.1 scfh. FCIC-12CV was disascembled~and was found to have a dirty seat causing improper seating. The seat was cleaned and valve reassembled. After reassembly and retest, the leakage was.09 scfh. RCIC-12CV is an Anchor 2", 600# check valve.

1

m

~

Mr. K. V. Scyfrit, Dirsctor June 30, 1981 Page 4.

X-223B Core Spray Pump "B" Minimum Flow Recirc Isolation.

The test volume for this penetration is between CS-MOV-M05B and CS-V-25.

Initial leaking tests showed a leak rate of 7.86 cfh. The established limit is 1.0 scfh. CS-MO-5B and CS-V-25 were both disassembled. New seat rings were installed in CS-MOV-5B and the gate was lapped followed by blue check of seats. The stem and seats of CS-V-25 were cleaned and reassembled with new gasket. After repair to the two valves, the retest leakage was.13 scfh. CS-MOV-M05B is an Anchor 3" gate valve and CS-V-25 is an Anchor 3" globe valve.

Per Section 4.7.A.2.f of the Technical Specifications, all valves were tested at > 58 psig with the exception of the MSIV's.

Pressure decay or water collection was used to determine the leakage. The total as-found leakage was approximately 505.8 cfm.

Of this, the uncontained leakage was determined to be less than 132.8 scfh. This leak rate does not exceed the equivalent of.6 La (189 scfh) of the primary _ containment volume per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 58 psig as addressed in Technical Specification Section 4.7.A.2.a. Page 160. After repair of the leaking valves, the leak rate was reduced to less than 136.5 scfh.

4 Sincerely,

- v-m L. C. Lessor Station Superintendent Cooper Nuclear Station LCL:cg

~

ARC FORM 366 U. S. NUCLEAR REGULATORY s JMMISSION

• (7-77)

~

LICENSEE EVENT REPORT CONTROL BLOCK: l l

l l

l l lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6

l0 l1l lN l El Cl Pl Rl 1l@l0 l0 l-l 0 l 0 l 0 l 0 l - l 0 l Ol 0l@l4 l1 l 1 l 1 l 1 l@l l

l@

7 8 9 LICENSEE CODE 14 lb LICENSE NUMBEH 25 26 LICENSE TYPE JO

$7 CAT 58 CON'T 5$R$ l Ll@l Ol Sl 0l 0l 0l 21 9l 8@l0l5l3l118l 11@l0l6l3l0l8l1l@

o 1 l

H 60 61 DOCKET NUMBER 68 69 EVENT DATE 14 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l o l 2 l l While performing local leak rate test procedure 6.3.1.1, twelve penetrations were 1 [o l3l lfound leaking excessively. Technical Specifications Section 3.7.4 requires the l

1014 l l primary containment leakage to be less than 189 scfh (.6 La).

The uncontained I

l o I s l I leakane was less than 132.8 scfh. UE 75-22 and LER's 77-57, 79-9 and 80-12 I

lo!611doacrihn n,rovinun ovonra nf chia nntnvo.

There was no significant occurrence as I

l o 17 l l a result of this event. There were no adverse effects to public health and i

I O Ia l ! safety.

l 7

8 9 80 DE CODE SUSC E COMPONENT CODE SUSC D'E SU DE lS lD l@ y@ W@ lV l A l L l Vl El Xl@ l Xl@ J @

o 9 7

8 9

10 11 12 13 1H 19 20 SE QUE N TI A L OCCUR R E NCE REPORT REVISION LE R EVENT YEAR REPORT NO.

CODE TYPE NO.

@ ag.RO l8l1l l-l l0 l1 l 5 l l/l l0l3l lL l

[---J W

_ 21 22 23 24 26 27 M

M 30 31 32 TAKEN AC ON ON PLANT MT HOURS S8 IT FO b

B.

SU PLI MANUF C URER IBl@{_Z_.j@

lf2__j@

[.Z _l@

l0l0l0l0l W@

l.__j@

lLl@

lZl9l919l@

33 34 35 36 JI 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l i l U l l Ten leaks were caused by normal valve wear, two by improper Limitorque operation.

I i i l Valve repairs were performed on one 24" AC butterfiv, one 24" Anchor gate, one 18" l li121lArchor gate, one 6" Anchor gate, two 3" Anchor gates, one 1" Anchor gate, one 8" l

l i l a i I Anchor niobe. one 3" Anchor clobe and one 2" Anchor check valve. One Limitorque l

najn= coa. Final leakage was less than 136.5 scfh.

l 11 141 I nnornent uns ronineod-nno unn 7

8 9 80 STA S ai, POWE R OTHER STATUS 15 OV RY DISCOVERY DESCRIPTION 32 d @ lO!0l0l@l NA l

U @l Local Leak Rate Testing l

i s ACTIVITY CONTENT l

RELE ASED OF RELE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE [yj @

@l NA l

l NA l

1 6

['

8 9 10 11 44 45 80 7

PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION 39 l

l 1 l 7 l l Ol 0l Ol@[Z_J@l NA l

I PERsONNe't iN;u7iES oESCRiPTiON@

numER i nlofol@l NA l

n 1

K 4 11 12 80 L USS OF OH DAMAGE TO F ACill TY TYPE DE SCHeP TION l'IolL1J@l l

NA l

r N 9 10 Punt u.: i j

NRC USE ONL Y I

l' f.U E D t ENCHtPflON l

lllllllll1lll 68 69 80 5 ennis K. h ker 0

NAME OF PREPARER PHONE:

o