05000280/LER-1981-023-03, /03L-0:on 810422,PT-39B-2 Indicated Snubbers to Be Inoperable Per Tech Spec 4.17.Caused by Leakage Around Valve Block or Through Connections at Reservoir. Inoperable Snubbers Replaced

/03L-0:on 810422,PT-39B-2 Indicated Snubbers to Be Inoperable Per Tech Spec 4.17.Caused by Leakage Around Valve Block or Through Connections at Reservoir. Inoperable Snubbers Replaced

ML18139B317
Person / Time
Site:	Surry
Issue date:	05/15/1981
From:	Joshua Wilson VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18139B315	List: 05000280/LER-1981-010-03, /03L-0:on 810415,alarm Setpoints for RM-CC-105 & RM-CC-106 Found Greater than Tech Spec Limits on Several Occasions.Caused by Misinterpretation of Background & Insufficient Guidelines for Evaluation of Alarm Setpoint 05000280/LER-1981-023-03, /03L-0:on 810422,PT-39B-2 Indicated Snubbers to Be Inoperable Per Tech Spec 4.17.Caused by Leakage Around Valve Block or Through Connections at Reservoir. Inoperable Snubbers Replaced ML18139B314
References
LER-81-023-03L-01, LER-81-23-3L-1, NUDOCS 8105200297
Download: ML18139B317 (2)

LER-1981-023, /03L-0:on 810422,PT-39B-2 Indicated Snubbers to Be Inoperable Per Tech Spec 4.17.Caused by Leakage Around Valve Block or Through Connections at Reservoir. Inoperable Snubbers Replaced

Event date:
Report date:
2801981023R03 - NRC Website

text

.;':JijC FOJ!M 366 ___ -

U.S. NUCI.EAR REGULATORY COMMISSION r,.771 LICENSEE EVENT REPORT e

'CONTROL. BI.OCK:

..I _.._

.........;_10 IPL.EASE PRINT OR TYPE Al.1. REQUIREC INFORMATION!

6 [iliJ I V ' A I s I p I s 12 101 0 I O I

~

S 9

LIC!:NSEE CODE 14 lS

- I o 1 01 01 01 01 -I 01 o 1014 11 111111101 I I© LICENSi: NUMBER 2S 26 LICENSE TYPE

JO 57 CAT SS

~;~~~; LI© I O I 5 I O I O l O l 21 8 J 1101 0 14 12 l 21 8 ) 11© I O I 5 11 I 5 1 8 I 1 10*

60 61 DOCKET NUMBER 68 69 EVENT CATE 7S REPORT DA,E 80 EVENT OESCi'llPTION ANO PROBABI.E CONSEQUENCES@)

l With the Unit at cold shutdown, PT-39B-2 ( Visual Inspection pf Tpaccessab]e Snubberd indicated snubbers 2-SHP-HSS-4A, 2-WFPD-HSS-3,6,8,9,.12 and 13 *to be inoperable oer

~

T.S.-4.17.

This is reportable per T.S. 6.6.2.b.(2),

The snubbers did allow expan-

((IT]

[ill]

[TII]

i]JIJ sion and contraction of the affected piping during the previous heatup and cooldown and no seismic events QCCUred since they Were last Verified Operable I Therefore the health and safety of the public were not affected.

7 8 9 IIITJ s

$'1'.STEM coos jc IHI@

9 10

CAUSE

CAUSE COMP.

cooe

• SUBCOOE COMPONENT COOE SUBCODE w@ w@ Is ju IP lo lR IT 1e IJLJ 11 12 13 18 19 VALVE SUBCODE lu@

.20 SEQUENTIAL -

OCCURRENCE REPORT REVISION c.:;,.

LER/RO CVENT YEAR REPORT NO.

CODE TYPE NO.

~

REPORT Is 11 I I I Io 12 1 3 I I.,...,

lo I 3 I lLJ 1-l I.LI NUM_BER 21 22 23 24 26 27 2S 29

. 30 31 32 so AC.ION FUTURE EFFEC:. -

SHUTDOWN

~ ATTACHMENT NPR~

PRIME C:OMP.

COMPONENT

'TAKEN ACTION ON PLANT METHOC HOURS @

SUBMITTEC FORM,liUB.

- SUPPUER MANUFACTURER W@)W@) W@ W l*O !of o !o I L!J@L l.!!J@)

W@) *-JG 12 15 15 I@)

33 34 3!i 36 37 40 42 43 "11 CAUSE OESCRIPTION ANO CORRECTIVE ACTIONS J The low level in the reservoir.s was due to leakage around the valve block or through OJI]

connections at the reservoir.

All inoperable snubbers were replaced.

CIJII [IliJ L.I ---------------------------------------i o:El 7

8 9

FACILITY

'30' STATUS

% POWER OTHER STATUS \\.:::;:I t.IIIl W@ jo !o I oj@)I _____

N/

__ A ___

7 B

9 10

.12 13 ACTIVITY CONTENT IC\\

RELEASEC OF RELEASE AMOUNT OF ACTIVITY ~

ITfil w L1J(§I

. N/A a 9 10 1,

80 METHOD OF DISCOVERY DESCRIPTION @

DISCOVERY I l]_J@I-Periodic Test.

44

,45 46 I

_LOCA,.;ON OF REL.EASE @

NIA 4S 80 I

BO PERSONNEL EXPOSURES Q

NUMBER t.:::\\ TYPE I,;;;\\ CESCRIPTION ~

ITITI 1 0 I O I O !'2;;W~1.-----.=.:N.1.aA~---------------------.J a s 11

,2 13 PERSONNEL INJURIES

~

NUMBER CESCRl"ION6 iITIJ I O 1 O I O I@

N A B

9 11 l.12--------~~-----------------------------80 LOSS OF OR DAMAGE TO FACILITY~

TYPE

DESCRIPTION

I;:::)

DJIJ W@

BO N

a a 10 so PUBLICITY C\\

NRC us-o v

ISSUEO~ DESCRIPTION~

i; NL.'

(I[§] L!Jei~ ________

N....;./_A ____________ ~_ ! ! I 1 I fl "1 I I I I -1 !

7 8

9 10

68. 69 so ;;

ei1.10NE:

(804) 357-3184*.

~

--- --** ~*---~---*

~---

w......

~*"'**--

". -* **.......,.. _...,... -~~"-----,- *-*

e ATTACHMENT l SURRY POWER STATION, UNIT 2 DOCKET NO:

50-281 REPORT NO:

8 l -023/03L-O EVENT DATE:

04-22-81 TITLE OF EVENT:

INOPERABLE SNUBBERS

1.

DESCRIPTION OF EVENT

With the Unit at cold shutdown, PT-39B-2 (Visual Inspection of lnaccessable Snubbers) was performed.

As the results, the following snubbers were evaluated as to be inoperable due to low oil in the associated reservoirs as per Tech. Spec. 4. 17:

2-SHP-HSS-4A, 2-WFPD-HSS:::3 2:..\\./FPD-HSS-6, 2-WFPD-HSS-8, 2-WFPD-HSS-9, 2-WFPD-HSS-12, and 2-WFPD-HSS-13.

This is reportable per Tech. Spec. 6.6.2.b(2).

2.

PROBABLE CONSEQUENCES AND STATUS OF REDUNDANT EQUIPMENT:

Snubbers are designed to prevent unrestrained plpe motion under dynamic loads as that might occur during an earthquake or a severe hydraulic transient.

In addition, they allow for normal thermal expansion and contraction during heatup and cooldowns.

The low oil Ln the re~evoV~s dld not preveht th~rmal ex~ansiori and contraction.

There had been no seismic events during the inspection interval.

Therefore, the health and safety of the public were not

~ffected.

3.. CAUSE:

The low level in the reservoirs was due to l~akage in the valve block connections or from the connections at the reservoir.

The snubbers were replaced prior to startup.

4.

IMMEDIATE CORRECTIVE ACTION

The immediate corrective action was to complete PT-39B-2 including the engineering evaluation of the snubbers.

5.

SUBSEQUENT CORRECTIVE ACTION:

The subsequent corrective action was to replace the inoperable snubbers.

6.

ACTION TAKEN TO PREVENT RECURRENCE:

None deemed necessary.

7. *.GENERIC IMPLICATIONS:

None.