ML19308D435

RO-77-90:on 770715,decay Heat Valve DHV-4 Failed to Open from Control Room During Quarterly Valve Cycling.Cause Not Determined.Corrective Action Will Be Initiated After Engineering Evaluation

ML19308D435
Person / Time
Site:	Crystal River
Issue date:	08/09/1977
From:	Stewart W FLORIDA POWER CORP.
To:
Shared Package
ML19308D411	List: ML19308D410 ML19308D435
References
NUDOCS 8002280744
Download: ML19308D435 (2)

Text

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l Fl Ll ClR lE l3 l l 0l 01-l 0 l 0 l 0l 0l 0l-l0 l 0l l4 l1 l1 l1 l1 l l 0l 3l 7 89 14 15 25 26 30 31 32 CATEGORY Typt S2 DOCKET NUMBEA EVENT CATE AEPCAT DA?E (CONT l ~ l ~ l 7 8 57 lb l l l l0l5l0l_l0l3l0l2l l 0l 7l 1l 5l 7l 7l l0 l8 l0 l9 l7 l7 l 58 59 60 61 68 69 74 75 80 EVENT DESCRIPTION a l During the performance of the quarterly cycling of valves surveillance procedure l 7 89 eo gg l Decay Heat Valve DEV-4 would not open from the control room contrary to Tech Spec 3.6.3q1.

7 89 -

30 0 l Redundancy was maintained with valve DHV-41. Second time occurrence, refer LER 77-9.

l 7 89 60 Q l A request for Engineering evaluation and assistance has been initiated. l 7 09 go O l (LER 77-90) l 7 89 m, SO E CDE COMPONENT CCCE SUPPLEA ACRMA VOLATON

@ lC) FI d 7 89 10 11 12 l VI Al Ll Vl d ')

17 W 43 44 lWl0l3l0l 47 lNl 48 CAUSE DESCRIPTION p {

g l The cause of this event is unknown as subsequent testing was performed with satisfactory l 7 a9 60 09 l valve operation. Upon receipt of the Engineering evaluation, corrective action to pre- l 5

f clude recurrence will be initiated. 8]

s  % PoWEA o m EA STATUS 06 OVE DISCOVERY DESCalPTON g 9 l El l0 l 9 l 2 l l NA l ]45 l NA l

7 0 10 12 13 44 48 80 ACTMTV CON TENT AELEASEo AMOUNT OF ACTMTV LoCAT*N OF AELEASE 1

7 8 9 J CF WRELEASE l 10 11 NA l 44 l

45 NA l  ;

80 PERSONNEL EXPOSURES NUMBER TYPE CESCRfPTCN M l 0l Ol 0l Wl 7 89 11 12 13 NA l 50 PERSCNNEL INJURIES NUMBER DESCAPTON M l 0l 0l 0l l NA l 7 89 11 12 a0 OFFSITE CONSEQUENCES 3E l NA l 7 89 go LOSS OR DAMAGE TO FACILITY TYPE CESCR'PTON .

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7 89 dl 10 NA LO l

PUSLIC!TY 1 i NA l l 7 89 v3 <

AcutTIONAL FACTORS VS u

, g SEE ATIACHED SUPPLEMENTARY INFORMATION 8002280779 I i

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NAME. W. P5 Stewart o

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v- PHONE: 813/866-4159 no n,. m  ;

, , SUPPLEMENTARY INFORMATION

1. Report No.: 50-302/77-90

2. Facility: Crystal River Unit #3

3. Report Date: 9 August 1977

4. Occurrence Date: 15 July 1977

5. Identification of Occurrenca:

Containment isolation valve DHV-4 failed to open contrary to Technical Specification 3.6.3.1.

6. Conditions Prior to Occurrence:

Mode 1 power operation.

7. Description of Occurrence: '.

At 2315, while performing the quarterly cycling of valves surveillance procedure SP-370, valve DHV-4 would not open from the control room. Reduudant valve DEV-41 was de-activated in the closed position and DEV-4 was removed from service for maintenance. During the

' maintenance testing of DHV-4, the valve operated satisfactorily. A request for Engin-

, eering assistance, 3-B-15-d dated 25 July 1977, has been initiated and problem is now being investigated.

8. Designation of Apparent Cause:

The cause of this event is unknown at this time. .

9. Analysis of Occurrence:

In the event of an Engineering Safeguard actuation, the Decay Heat drop line could not have been used, in that DHV-4 is located in the Reactor Building and could not have been opened. The alternate long-term post-accident cooling path was operable and available.

10. Corrective Action:

Upon receipt of reconsnandation from the Engineering Department's evaluation, corrective action to preclude recurrence will be initiated.

11. Failure Data:

This was the sesed reportable occurrence of DHV-4 failing to open. Refer to LER 77-9, dated 9 February 1977.

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