ML18153A066

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Forwards Response to Violations Noted in NRC Insp Repts 50-280/96-08 & 50-281/96-08.Corrective Actions:Hydrogen Analyzer Instrument Calibr Procedures Revised to Provide Instructions for Placing FSS on Local & Remote Panels
ML18153A066
Person / Time
Site: Surry  
Issue date: 09/12/1996
From: OHANLON J P
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
96-425, NUDOCS 9609170471
Download: ML18153A066 (7)


See also: IR 05000280/1996008

Text

12, 1996 United States Nuclear Regulatory

Commission

Attention:

Document Control Desk Washington, D. C. 20555 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 REPLY TO A NOTICE OF VIOLATION

Serial No.96-425 SPS/BCB/GDM

R3 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 NRC INSPECTlON

REPORT NOS. 50-280/96-08

AND 50-281/96-08

We have reviewed your Inspection

Report Nos. 50-280/96-08

and 50-281/96-08

dated July 11, 1996, and your August 16, 1996 letter and enclosed Notice of Violation

for Surry Units 1 and 2. As discussed

in the attachment, the cited violations

resulted from inadequate

change management

when the hydrogen analyzers'

calibration

procedures

were changed. This conclusion

is based on the results of a Root Cause Evaluation

of the event. We have implemented

corrective

actions to resolve the specific concerns associated

with the violations, as well as more comprehensive

actions to ensure that similar concerns do not exist. Although the violations

were precipitated

by events that occurred at Surry several years ago, we recognize

that the procedure

change process should have identified

the procedural

interface

discrepancy.

This process was subsequently

strengthened

in the early 1990s and was recently enhanced further to preclude a similar event. We have no objection

to this letter being made a part of the public record. Please contact us if you have any questions

or require additional

information.

Very truly yours, ~?.~ James P. O'Hanlon Senior Vice President

-Nuclear Attachment

9609170471

960912 PDR ADOCK 05000280 G PDR ~--** .~. -*

1----:--cc: U.S. Nuclear Regulatory

Commission

Region II 101 Marietta Street, N.W. Atlanta, Georgia 30323 Mr. R. A. Musser NRC Senior Resident Inspector

Surry Power Station

NRC INSPECTION

CONDUCTED

JUNE 17 -JULY 1, 1996 SURRY POWER STATION UNITS 1 AND 2 INSPECTION

REPORT NOS. 50-280/96-08

AND 50-281/96-08

NRG COMMENT: "During an NRG inspection

conducted

on June 17 through July 1, 1996, violations

of NRG requirements

was identified.

In accordance

with the 'General Statement

of Policy and Procedures

for NRG Enforcement

Actions,'

NUREG-1600, the violations

are listed below: A. Technical

Specifications

3.7.G.1 requires that two independent

containment

hydrogen analyzers

be operable during reactor critical or power operation.

Contrary to the above, the Unit 1 and Unit 2 containment

hydrogen analyzers

were inGperable

during reactor critical or power operation

from February 28, 1991, and October 21, 1990, respectively, until May 22, 1996, due to the function selector switches being place in the ZERO position following

calibration.

(01013) B. Technical

Specifications

6.4.A.1 and 6.4.A.2 require, in part, that detailed written procedures

with appropriate

instructions

be provided for the operation, calibration

and testing of all systems and components

involving

nuclear safety of the station. Contrary to the above, from October 24 and October 20, 1990 for Units 1 and 2, respectively, Emergency

Operating

Procedures*

1-E-1 and 2-E-1, 'Loss of Reactor or Secondary

Coolant,'

and Calibration

Procedures

1-IPT-FT-GW-A-104

and 2-IPT-FT-GW-A-204, Containment

Hydrogen Analyzer H2A-GW-104(204)

Quarterly

Functional

Test, did not provide appropriate

instructions

to place the hydrogen analyzers (systems involving

nucle_ar safety of the station) in service. Specifically, the procedures

did not require placing the function selector switches for the-hydrogen analyzers

in the SAMPLE position, which is the required position for sampling the containment

atmosphere

for hydrogen concentration.

(01023) This is a Severity Level Ill problem (Supplement

I)."

L__ ---Violation

A REPLY TO A NOTICE OF VIOLATION

NRC INSPECTION

CONDUCTED

JUNE 17-JULY 1.1996 SURRY POWER STATION UNITS 1 AND 2 INSPECTION

REPORT NOS. 50-280/96-08

AND 50-281/96-08

1. Reason for the Violation, or, if Contested, the Basis for Disputing

the Violation

The violation

is correct as stated and was caused by inadequate

change management.

When the containment

hydrogen analyzers'

calibration

procedures

were changed to leave the function selector switch (FSS) on the local and remote panels in the ZERO position, the emergency

operating

procedures (EOP) did not include instructions

to reposition

the FSS to the SAMPLE position when placing the hydrogen analyzers

in service. Although the ZERO pesition is acceptable

for standby operation, the FSS must be in the SAMPLE position for the hydrogen analyzers

to be capable of performing

their design function.

At the time of the subject change to the calibration

procedures, a review of interfacing

procedures

was not required by the procedure

change process. Consequently, a review of the interfacing

procedures

was not performed

and the need to change the EOPs was not recognized.

As a result, a complementary

change was not incorporated

into the EOPs. This procedural

discrepancy

resulted in the FSSs being left in the ZERO position following

calibration, thereby rendering

the containment

hydrogen analyzers

inoperable

for an extended period of time. 2. Corrective

Steps Which Have Been Taken and the Results Achieved A Deviation

Report was submitted

to document the subject discrepancy.

l&C and System Engineering

personnel

reviewed the vendor manual for the hydrogen analyzers

to confirm the optimum operational

position for the FSSs. The FSS on the local and remote panels were placed in the SAMPLE position on May 22, 1996. The hydrogen analyzer instrument

calibration

procedures

were revised to provide instructions

for placing the FSS on the local and remote panels in the SAMPLE position following

calibration.

This is the required position to place the hydrogen analyzers

in service using the emergency

operating

procedures.

' . I I

  • 2. Corrective

Steps Which Have Been Taken and the Results Achieved (Cont'd.)

A Root Cause Evaluation (RCE) of the event was performed.

The results are summarized

in Section 1 above. The RCE also determined

that the North Anna Power Station operator watchstation

logs periodically

verified the position of the hydrogen analyzers'

FSSs, and that the Surry logs did not. The Surry operator watchstation

logs were subsequently

revised to include a periodic verification

that the FSSs are positioned

correctly.

In addition, a comparative

review of the North Anna and Surry Power Stations'

operator watchstation

logs was performed

to evaluate the commonality

of equipment

checks performed

at each station. No safety equipment

inconsistencies

were identified.

The Te.cbnical

Specifications

and emergency

and abnormal procedures

were reviewed by Operations

and l&C personnel

to evaluate infrequently

performed

evolutions

and post-accident

manual actions to determine

whether additional

procedural

interface

concerns existed. No additional

examples were identified.

The procedure

change process has been revised and improved since the subject hydrogen analyzer calibration

procedure

changes were processed.

These improvements

are discussed

in our response to Violation

B. 3. Corrective

Steps Which Will be Taken to Avoid Further Violations

The corrective

actions discussed

in Section 2 are sufficient

to avoid further violations.

A synopsis of this event is being presented

during the current continuing

training sessions to enhance the operators'

knowledge

and understanding

of hydrogen analyzer operation.

Training will also be conducted

for l&C technicians

during the next l&C continuing

training sessions.

4. The Date When Full Compliance

Will be Achieved Full compliance

was achieved on May 22, 1996 when the FSS on the local and remote panels were placed in the SAMPLE position .

Violation

B 1. Reason for the Violation, or, if Contested, the Basis for Disputing

the Violation

The violation

is correct as stated. As discussed

in Section 1 of Violation

A, a review of interfacing

procedures

was not performed

when the hydrogen analyzers'

calibration

procedures

were changed. The procedure

change process in place at the time the position of the FSSs was modified did not ensure that interfacing

procedures

were considered

for potential

impact. As a result, when the calibration

procedures

were changed to specify that the FSSs be left in the ZERO position following

calibration, the emergency

operating

procedures

were not changed to provide instructions

for placing the FSSs in the SAMPLE position when placing the hydrogen analyzers

in service. 2. Corrective

Steps Which Have Been Taken and the Results Achieved As discblSsed

in Section 2 of Violation

A, the hydrogen analyzer instrument

calibration

procedures

were revised to provide instructions

for placing the FSS on the local and remote panels in the SAMPLE position following

calibration.

This is the required position to place the hydrogen analyzers

in service using the emergency

operating

procedures.

The procedure

change process has been revised and improved since the subject hydrogen analyzer calibration

procedure

changes were processed.

Procedure

revisions

and upgrades have been centralized

under the Procedures

Department, and a technical

procedures

writer's guide has been developed

to standardize

format, style, content, and human factors considerations.

A technical

review is required for new and revised procedures, and technical

review guidelines

have been established

which address procedural

methods, instructions, and configuration

controls.

In addition, administrative

procedure

VPAP-0502, "Procedure

Process Control," has been revised to require an elevated level of review and approval when a procedural

revision or change alters the as-left condition

of a system or component.

This revision also added references

to the Licensee Event Report and NRG Inspection

Report associated

with this violation.

3. Corrective

Steps Which Will be Taken to Avoid Further Violations

The corrective

actions noted in Section 2 of Violations

A and B above are sufficient

to avoid similar violations.

    • * * 4. The Date When Full Compliance

Will be Achieved Full compliance

was achieved on September

3, 1996 when VPAP-0502

was revised .