ML20086B474

AO 50-267/74-9:on 740507,two Rod Groups Withdrawn During Low Power Physics Tests Violating Procedures.Caused by Misinterpretation of Record Requirements.Sys Checkoff Lists Will Be Modified

ML20086B474
Person / Time
Site:	Fort Saint Vrain
Issue date:	05/29/1974
From:	Mathie F, Swart F PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20086B470	List: ML20086B468 ML20086B472 ML20086B474
References
AO-50-267-74-9, NUDOCS 8311170444
Download: ML20086B474 (6)

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1 Date: flay 239,,'1974 ABSOPO!AL OCCURRENCP.

FORT Sf. VPAIN I;UCLEAR GENEPATING STATION

}'UBLIC SERVICE t.0:?A';Y OF COLORADO

, P. O. BOX 361 ,

PLATTEVILLE, COLORADO 80651 . .

REPORT No. 50-267/74/9 Preliminary 0 '

Final X i

IDENTIFICATION OF OCCURREC!:: .

The following occurrence is considered an Abnormal Occurrence under defi-nition 2.13 of the Technical Specifications.

On May 7, 1974, following evacuation and backfill of the reactor vessel with helium, preparations were being made to take the reactor critical to determine the difference in critical rod height with the core in air and helien. The reactor cas never taken critical. Only tuo rod groups were i withdrawn. .

This operati n uas considered a violation of Criterion XVII of Appendix B to 10CFR50, insofar as the procedures being used, and the prercquisite check lists, were not signed off to indicate that they had been followed.

4 CONDITIONS PRIOR TO OCCURKENCE: Steady State Pouer Routine Shutdown. *

! Ilot Shutdown Routine Load Change i .,

Cold Shutdown X Other (specify)

Refueling Shutdown Low Power Physics Tests-

. Routine Startup Reactor in liclium 8311170444 740530 PDR ADOCK 05000267 S PDR 1

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The inajcr plant parancters at the time of the event were as follows:  !

power PTR, 1/A Inith  !

1 ELECT, N/A MWe ,

Secondary Ceolant Pressure N/A psig .

I Temperature N/A *F  ;,

Flow -_

N/A #/hr. .,

Pritaary Coolant Presourc 78 psig Temperature 100 *F Core Inlet

• 100 *F Core Outlet Flow N/A #/hr.

DESCRIPTION OF OCCU P.RT'!CE :

un May /, 1974, pteeat div.m . crc. in Frc;;ra00 te tch0 tha "aaernv crirical in heliua inmediately follouing backfill of the renctor vessel to determine the change in critical red height uith the reactor in hellun as compared to those critical red heights necsured in air. In addition, data was to be taken to determine the extent of a suspected probica concerning per:r.anent source placcment and strength and their effect on the 1/M Curve for predicting criticality.

Uc were questioned by the local Regulatory Operations Inspector as to the usage of a procedure, and the checking of prcrcquisites (or use of the pre-critical check-off lists).

The appropriate procedure u s being used but personnel had not signed off steps as they procrossed through the procedure to provide a record of pro-cedural use.

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l Page 3 APPAlu;ST CAUSE OF GCCURRENCE: Design Unusual Service Cond.

Including Environnent Manufacture Component Failurc Installation /Const. X Other (specify)

Operator Misinterpretntion of record Procedure requirements.

A!!ALYSIS OF OCCURFENCE:

• 9 Pursuant to Technical Specificatien 7.1.2, the Plant Operations Revicu Cormittee (PORC) was ccnvened to investigate the violation of Criterion XVII of Appendix B to 10CFR50.

The PORC concluded that there was a misunderstanding as to the required -

recording during secrtup tests, cnd operations donc according to an Over-all Plant Operatirs Procedure or Systen Operating Procedure.

CORRECTIVE ACTION:

The following recormendations were submitted by the Plant Operations Re-vicw Cctaittee and approved for implimentation:

1. The System Check Off lists in the OPOP shall be modified to read in part:

"(System Operating)(Pre-Operational Valve Lineup) per SOP ",

rather than Pre-Operational Lincup Accordin; to S0P com-plcted.

2. In one (1) above, when Pre-Operational Valve lineup is used a checked of f signed copy shall be attached to the Systcu Check List.

3. When valve is set out of position in accordance with Pre-Operationcl Valve List an explanation is to be included along with Mech./Elcet.

Clearance Number, if applicable.

4. On Systen Check Lists in the OPOP uhen a piece of equipment is checked inoperabic, a brief explanation of inoperability should l be included in remarks and the Mcch./ Elect. Clearance Number, if i

applicable.

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5. Valve lists for various systems shu .I be segnented to cover "functionni units" uithin the syst.

6. For .those s.ystems in which individr .1 functional operations require rqnual valve operations, i.e., Systems 23, 24, 61, 62, 63, 92, etc., the associated functional valve list shall be checked and signed off and retained in the records.

Example: 1. Radioactive Waste Relcases - 62, 63.

2. Regeneration or Activation 1.ctivitics'- 23.

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7. When a picec of cquipment is removed from service for mainten-ance, the " Standard Clcarance Points" shall be used.

A signature block'for " valves returned to normal position" shall be added.

Upon return of the Mech./Elcet. cicarance, and return of equip-nent to cervice, the " Standard Clearance Points" should be signed and attached to the Mech / Elect clearance for the record.

8. h* hen clearing out a piece of equipment or vaJve for maintenance for which no forral " Standard Clearance Points" exists, a list of " Standard Clearance Points" shall be made out and signed and attached as in seven (7) above.

9. Operations per the SOP will be covered by norual leg entries. In

. general, no SOP sign off's are required. The SOP's are to be actively utilized and the operators are to log this in their daily logs.

To inplement the aforencationed philosophy, an Administrative Policy shall be issued by station managenent which will say in part:

The following shall be completed, signed of f, and retained in the record:

1. Pre-critical Instrument Check and OPOP Check Lists.

When the reactor is to be started following a shutdown with pouer

. operation centemplated, all Systen Check Lists and both Pre-Critical Instrument Check Lists shall be completed for power operation.

If the reactor is to be operated in the low power mode, less than 2% power, the Pre-critical Instrument Check, C.1, is required to be conpleted.

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2. OPOP Chech List.

Uhen thc reactor is to be operated from a shutdown condition or operations carried out in accordance uith the OPOP, the respec- .

tive OPOV Check ' List is to be completed. .

3. System Valve Lists.

When a systen ic being cet up initially before the initial rise to power, in shutdown during refueling or undergoes entensive .

maintenance, or tr.odification, during a refueling shutdoun, a complete valve lineup nhall be nade including valve 31st sign off and retention in the station records.

4. Documentetion of Punctional Operation Within a Systen. ,

1 a a) Systen 23 b) Systen 24 c) Systen 61 d) Syctc= 62 e) Systen 63 -

f) Systen 92 Uhen separate functional operations are performed within the above listed systems, ic; Eccencrations, liquid or gaseous relocscs, fuel transfer, etc., those portions of the valve list associated with

• the operation shall be proper 3y sit ned off and attached to the re-lease forn, if applicable, or otherwise retained for the record.

5. When a piece of eqbipment is removed from service for paintenance, the " Standard Clearance Points" record shall be properly filled in, signed, and attached to the Clearance Card for the record.

The implementation of the Mministrative Policy and philosophy ndopted will require review and modification of the OPOP Check Lista, revicy of valve lincup lists and addition of provisions for sign of f, and addition of provisions for sign off to the lists of " Standard clearance Points" used for c1 caring equipment out for maintenance.

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FAII,URE DATA / .

SIMI!.A!! OCCUI:RE::CT.S:

No similar occurrences of this type reported.

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_PROGl:N!'IATIC I:! PACT:

• No pror,rammatic impact.

CODF. I!! PACT:

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Prepared by: Approved:

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Franh ::athie Jabin.e..

Frederic b.r t't)4 E. S.:t

' Maintenance Ent;incer Superintendent Fort St. Vrain ::uclear Fort St. Vrcin :uclear Generating Station Generating Station I