ML20064F102

/01T-0 on 781102:during Post-Core Hot Functional Test,Prior to Initial Criticality Mode 3 Oper,Lift Setpoints of Main Steam Line Code Safety Valves Were Nonconservative. Caused by Incorrect Identification of Simmer Point

ML20064F102
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/16/1978
From:	Shively C ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20064F097	List: ML20064F092 ML20064F102
References
LER-78-010-01T, LER-78-10-1T, NUDOCS 7811280211
Download: ML20064F102 (4)

Text

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1. Reportabic Occurrence Report TJo. 50-368/78-10 '

2. Report Date: 11-16-78 3. Occurrence Date: 11-02-78 4 Facility: Arkansas Nuclear One - Unit 2 Russellville, Arkansas

5. Identification of Occurrence:

Testing of main steam line code safety valves revealed that setpoints were less thar. conservative.

6. Conditions Prior tc Occurrence:

Steady-State Power Reactor Power 0 MWth Hot Standby _

Net Output 0 Mwe Cold Shutdown Percent of Full Power 0 g Refueling Shutdown Load Changes During Routine Power Operation 0 Routine Startup Operation Routine Shutdown Operation Other (speci fy) X Preoperational, Startup or power ascension tests

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7. Description of _0ccurrence:

Prior to initial criticality, Mode 3 operation, a procedure identified the simmer points of the main line code safety valves as being less than conservative.

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1-i Reportable Occurrence P.eport No. 50-368/78-10

8. Designation of Apparent Cause of Occurrence:

, Design Procedure X Manufacture Unusual Service Condition

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Including Environmental Installation /

, Construction Component Failure (See Failure Data)

Operator A

Other (specify)

9. Analysis of Occurrence:

As a result of the occurrence, the blowback associated with testing of 2PSV-1002 was excessive and. is reported as required by Technical Specification 6.9.1.8.e.

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10. Corrective Action:

The procedure was modified and all valves were readjusted and verified by actual steam lift.

11. Failure Data:

There have been no similar occurrences.

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. e WM AAKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 VTTLE ROCK. ARKANSAS 72203 (501)371-4000 November 16, 1978 2-118-15 Mr. K. V. Seyfrit, Director l Office of Inspection G Enforcement /

U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011

Subject:

Arkansas Nuclear One - Unit 2 Docket No. 50-368 ,

License No. NPF-6 Reportable Occurrence Report

, No. 50-368/78-10

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(File: 2-0520)

Gentlemen:

In accordance with Arkansas Nuclear One-Unit 2 Technical Specification 6.9.1.8.e, we have attached the subject report concerning the nonconser-vative lift setpoints of the main steam line code safety valves.

Very truly yours, p.~<.' s< ,G

- f[.DanielH.

Manager, Williams Licensing

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1. Reportabic Occurrence Report No. '

50-368/78-10.

2. Report Date: 11 16 3. Occurrence Date: 11-02-78

,' 4 Facility

Arkansas Nuclear One - Unit 2

\ Russellville, Arkansas

'5. ~ Identification of Occurrence:

Testing of main steam line code safety valves revealed e

,that setpoints were less than conservative.

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6. Conditions Prior to Occurrence:

Steady-State Power Reactor Power 0 MWth Hot Standby Net Output 0 MWe 4 Cold Shutdown Percent of Full Power 0 g .

Refueling Shutdown Load Changes During Routine

. Power Operation 0 Routine Startup Operation Rautine Shutdown Operation. s t

Other (specify) X Preoperational, Startup or power ascension tests t

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7. Description of Occurrence:

Prior to initial criticality, bbde 3 operation, a procedure '

identified the simmer points of the main line ' code safety valves as being less than conservative.

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Reportable Occurrence Report No. 50-368/78-10

8. Designation of Apparent Cause of Occurrence:

Design . Procedure X

- Fbnufacture Unusual Service Condition Including Environmental Installation /

Const ruction Component Failure (See Failure Data) .

Operator ,

Other (specify)

9. Analysis of Occurrence:

As a result of the occurrence, the blowback associated with testing of 2PSV-1002 was excessive and is reported as required by Technical Specification 6.9.1.8.e.

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1 Reportable Occurrence Report do. 50-368/78-10

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. 10. Corrective Action

4 The procedure was modified and all valves were readjusted and verified by actual steam lift. ,

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11. Failure Data:

t There have been no similar occurrences.

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