ML20214V421

Rev 0 to TVA Employee Concerns Task Group,Other Sites:Nrc Insp 327, 328/84-35:Valve Checklist;Fuel Handling Instruction

ML20214V421
Person / Time
Site:	Sequoyah
Issue date:	10/08/1986
From:	Debbage A, Gass K, Knightly J TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20214T770	List: ML20214T769 ML20214T773 ML20214U886 ML20214U902 ML20214U929 ML20214U950 ML20214V344 ML20214V377 ML20214V398 ML20214V421 ML20214V447 ML20214V506 ML20214V523 ML20214V546 ML20214V593 ML20214V615 ML20214V628 ML20214V649 ML20214V673 ML20214V686 ML20214V705 ML20214V728 ML20214V767 ML20214V774 ML20214V800
References
SWEC-SQN-19, SWEC-SQN-19-R, SWEC-SQN-19-R00, NUDOCS 8612090678
Download: ML20214V421 (6)

Text

p-TENNESSEE VALLEY AUTHORITY

, WATTS BAR NUCLEAR PLANT EMPLOYEE CONCERNS TASK GROUP OTHER SITES CEG Element

Title:

NRC Inspection 327, 328/84-35:

Valve Checklist; Fuel Handling Instruction SWEC Concerns: A02850103007-001 '

A02850103007-002 Source Document: NRC Inspection Report 327, 328/84-35 Report Number: SWEC-SQN-19 Evaluator: If A a A /o - 9.- V t, K. R. Gass Date Reviewed by: NCl /O -f -f[0 J. J. Knightly Date Approved by: 4 eILa> /d A. G. Debba{e Date[gg 1940T 8612090678 DR 861120 p ADOCK 05000327 PDR

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Report SWEC-SQN-19 l NRC Report Numbers 327, 328/84-35 i l

I. INTRODUCTION During an inspection conducted on November 6 through December 5, 1984, (Reference 1) the Nuclear Regulatory Commission (NRC) inspector identified one violation and an Inspector Followup Item (IFI) which were included in the Stone & Webster Engineering Corporation (SWEC) systematic analysis:

A02850103OO7-001 (Violation 327, 328/84-35-01) Inadequate Valve Checklist.

A02850103007-002 (IFI 84-35-04) Inadequate Fuel Handling Procedure.

Information on the background, the corrective actions taken, the verification methodology, the verification analysis, the completion status, and any pertinent references for the area of concern is included in this re port.

II. VERIFICATION OF SWEC ISSUE A. A02850103007-001, Inadequate Valve Checklist

1. Background - Technical Specification 6.8.1 requires that written procedures be established, covering activities referenced in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.

Paragraph 3 of Appendix A requires specific procedures for the Emergency Core Cooling System (ECCS). System Operating Instruction (SOI)-63.1, " Emergency Core Cooling System," was established to satisfy this requirement.

Contrary to the above, adequate procedures were not established in that Valve Checklists 63.14-3 and 63.1A-4, Revision 26, of SOI--63.1, Revision 30, each failed to list a level transmitter root valve for the cold leg accumulators. This was identified as NRC violation 84-35-01.

2. Corrective Actions Taken - In their response (Reference 2), SQN stated that a temporary change was made to the procedure involved on November 29, 1984, to include the missing root valves. On December 12, 1984, the temporary procedure change became a permanent revision.

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, 3. Verification Methodology - The SWEC concern identified for Employee Concerns Task Group (ECTG) verification was stated as follows:

RIMS # ISSUE RIMS ITEM A02850103007 Adequate Procedures RIMS-001 were not established in that valve checklists did not list a level transmitter root valve for cold leg accumulators ECTG reviewed the Sequoyah Compliance Licensing Files for internal and external correspondence related to this issue, applicable procedures, and NRC status and closure files. This review of the pertinent documentation formed the basis for this verification activity.

4. Verification Analysis - The ECTG review of the pertinent documents indicated that the corrective actions for this concern and the violation have been completed. SOI-63.1 was verified to include the two missing level transmitter root valves for the cold leg accumulator. The NRC closed violation 84-35-01 in report 85-26, (Reference 3).

5. Completion Status - Based on completion of SQN corrective actions and closure of the NRC violation, this SWEC concern is closed.

B. A02850103OO7-002, Inadequate Fuel Handline Procedure

1. Background - During a review of Fuel Handling Instruction, (FHI)-7, " Refueling Operation," the inspector questioned the meaning of Precaution H of the procedure which allows interlocks on the fuel handling system to@e bypassed only with the approval of and under the direct supervision of the Fuel Handling Senior Reactor Operator (SRO). SQN indicated that this applied to non-Technical Specification interlocks, except in emergencies, and required additional site management input. SQN was to review FHI-7 and make revisions as appropriate to provide:

clarification on which interlocks cannot be bypassed without the formal administrative controls of Technical Specification 6.8. ,

- proceduralized requirements on the actions to be taken when interlocks are bypassed.

requirements for additional fuel transfer ,1ystem checks when transferring fuel elements containing Rod Cluster Control Assembly (RCCA), since these elements have significantly less clearance with the tube flange during upender operation.

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This was identified as inspector followup item 328/84-35-04.

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2. Corrective Action Taken - SQN's response (Reference 5) to a related issue (Violation 84-36-01, Inadequate Implementation of FHI-7) included the scope of the IFI 84-35-04. SQN stated that equipment modifications and FHI-7 procedural change would be accomplished to improve fuel handling.

3. Verification Methodology - The SWEC concern identified for ECTG verification were stated as follows:

RIMS # ISSUE RIMS ITEM A02850103007 Lack of clarification RIMS-OO2 and specific require-ments in fuel handling instructions had an adverse affect on refueling activities.

ECTG reviewed the Sequoyah Compliance Licensing Files for internal and external correspondence related to this issue, applicable procedures, and NRC status and closure files. This review of the pertinent documentation formed the basis for this verification activity.

4. Verification Analysis - The ECTG review of the pertinent documents indicated that the corrective actions for this concern have been completed. The NRC IFI was still open August 1986; however, the NRC closure statement (Reference 4) for the related violation 84-36-01 indicated corrective action had been satisfactorily accomplished as follows:

The licensee has specified in fuel handling instruction . ..

that all interlocks are to be checked out and functional.

Also, if it is necessary to bypass an interlock, the procedure requires approval by the refueling SRO and clear documentation of the event. Further, before raising the upender, the licensee's instruction requires visual verification that the fuel assembly and any inserts will clear the transfer tube flange. The verification is done by means of an underwater TV system. The violation is considered closed.

5. Completion Status - SQN corrective actions have been completed.

This SWEC concern can be closed following closure by the NRC.

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III. REFERENCES

1. NRC Inspection Report Numbers 50-327/84-35 and 50-328/84-35, dated December 28, 1984, D. M. Verrelli to H. G. Parris

2. TVA Memorandum, " Response to NRC-OIE Inspection Report Numbers 50-327/84-35 and 50-328/84-35," dated January 21, 1985, R. H. Shell to J. P. O'Reilly

3. NRC Inspection Report Numbers 50-327/85-26 and 50-328/85-26, dated September 6, 1985, R. O. Walker to H. G. Brown

4. NRC Inspection Report Numbers 50-327/85-44 and 50-328/85-44, January 14, 1986, D. M. Verrelli to H. G. Parris

5. TVA Memorandum, "Sequoyah Nuclear Plant - NRC - OIE Inspection Report Number 50-328/84-36," dated February 20, 1985, from R. H. Shell to J. N. Grace Page 4 of 4 L

TVA EMPLOYEE CONCERNS REPORT NUMBER: SWEC-SQN-19 SPECIAL PROGRAM REPORT TYPE: Sequoyah Nuclear Plant Element REVISION NUMBER: 0 TITLE: Valve Checklist; Fuel Handling Instruction REASON FOR REVISION: N/A SWEC

SUMMARY

STATEMENT: The items in this report were identified by the Nuclear Regulatory Commission (NRC) and were included in the Stone & Webster Engineering Corporation (SWEC) systematic analysis. All items evaluated within this report were verified to be adequately addressed and SWEC concern A02850103007-001 was closed by NRC. Concern A02850103007-002 is now ready for closure.

PREPARATION PREPARED BY:

WS 'A //-/2-$(,

SIGNATURE DATE REVIEWS PEER:

S 4 SIGNATURE lifil Y DATE AN Aff // ) 6(G SIGNATURE DATE l CONCURRENCES I

l CEG-H: Sv lll12lt(,

SRP: . dLes44 //-/5 - TC j SIGNATURE DATE SIGNATURE

• DATE i APPROVED BY:

} })/L' ll~lY'$$ N/A f ECSP MANAGkt DATE MANAGER OF NUCLEAR POWER DATE CONCURRENCE (FINAL REPORT ONLY)

] *SRP Secretary's signature denotes SRP concurrences are in files.

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