ML19308D435
| ML19308D435 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 08/09/1977 |
| From: | Stewart W FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML19308D411 | List: |
| References | |
| NUDOCS 8002280744 | |
| Download: ML19308D435 (2) | |
Text
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UCENSEE EVENT REPORT 4
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?v'PE uCENSE ~OuSEA 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 lb l l
l l0l5l0l_l0l3l0l2l l 0l 7l 1l 5l 7l 7l l0 l8 l0 l9 l7 l7 l 7 8 57 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 SO m,
E CDE COMPONENT CCCE SUPPLEA ACRMA VOLATON
@ lC) FI d l VI Al Ll Vl d ')
W lWl0l3l0l lNl 7 89 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION p
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g l The cause of this event is unknown as subsequent testing was performed with satisfactory l 7 a9 60 l valve operation. Upon receipt of the Engineering evaluation, corrective action to pre-l 09 5
f clude recurrence will be initiated.
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% PoWEA o m EA STATUS 06 OVE DISCOVERY DESCalPTON g
l El l0 l 9 l 2 l l NA l ]
l NA l
7 0 9
10 12 13 44 45 48 80 ACTMTV CON TENT AELEASEo CF RELEASE l AMOUNT OF ACTMTV LoCAT*N OF AELEASE W
NA l
l NA l
J 1
7 8 9
10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE CESCRfPTCN M l 0l Ol 0l Wl NA l
7 89 11 12 13 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 1 ~ dl NA l
7 89 10 LO PUSLIC!TY 1
i NA l
7 89 v3 AcutTIONAL FACTORS VS u
8002280779 g
SEE ATIACHED SUPPLEMENTARY INFORMATION I
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i NAME. W. P5 Stewart PHONE: 813/866-4159
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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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