ML20214J206

Rev 0 to TVA Employee Concerns Special Program Rept SWEC-SQN-16, Surveillance Instruction Inadequacy

ML20214J206
Person / Time
Site:	Sequoyah
Issue date:	11/13/1986
From:	Birchell R, Knightly J, Stewart D TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20214H850	List: ML20214H848 ML20214H865 ML20214H879 ML20214H927 ML20214H956 ML20214H976 ML20214J008 ML20214J040 ML20214J053 ML20214J064 ML20214J083 ML20214J093 ML20214J101 ML20214J126 ML20214J135 ML20214J144 ML20214J161 ML20214J169 ML20214J180 ML20214J199 ML20214J206 ML20214J212 ML20214J220 ML20214J224 ML20214J231 ML20214J243 ML20214J251 ML20214J261
References
SWEC-SQN-16, SWEC-SQN-16-R, SWEC-SQN-16-R00, NUDOCS 8612010205
Download: ML20214J206 (6)

Text

TVA EMPLOYEE CONCERNS REPORT NUMBER: SWEC-SQN-16 SPECIAL PROGRAN REPORT TYPE: Sequoyah Nuclear Plant Element REVISION NUMBER: 0 TITLE: Surveillance Instruction Inadequacy REASON FOR REVISION: N/A

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SWRC

SUMMARY

STATENENT: The items in this report were identified by the Nuclear h

Regulatory Commission (NRC) and were included in the Stone & Webster Engineerint j Corporation (SWEC) systematic analysis. All items evaluated within this report k were verified to be adequately addressed and SWEC concerns A02 841214 002 -001 i and -003 were closed by the NRC. Concern A02 841214 002 -002 is now ready for closure.

PREPARATION 1 PREPARED BY:

"h?0 /S ' A br f.e.B L AD/ n-c- 2 L

/ShntATURE DATE l

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REVIEW 5 PEER:

i & C4 MS '

uMeh SIGNATURE DATE Y

• Nb SIGNATURE DATE CONCURRENCES CEG-H: h // /t./f /.

SRP:  % _k ll*l2 *N SIGNATURE DATE G SIGNATURE

• DATE APPROVED BY' MVki&> -

thi3-n NiA ECSP MANADER DATE MANAGER OF NUCLEAR POWER DATE CONCURRENCE (FINAL REPORT ONLY) q 'SRP Secretary's signature denotes SRP concurrences are in files.

l 2242T 8612010205 861117 PDR ADOCK O$000327 P PDR

TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT EMPLOYEE CONCERNS TASK GROUP j OTHER SITES

! CEG 1

.i j Element

Title:

Surveillance Instruction Inadequacy SWEC Concerns: A02841214002-001

! A02841214002-002 l A02841214002-003 1

1 j Source Document: NRC Report 50-327/84-29 and 50-328/84-29 Report Number: SWEC-SQN-16 1

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Evaluator: f(. /d .3 h[

l R. C. Birchell' datt Reviewed Dy: TC b '

IO[*l[$

J. J. Knightly Date Approved By: .e/

/d/ 7[gg, A. G. Debbde Date 1093T

s 3 Report SWEC-SQN-16 NRC Report 50-327/84-29 and 50-328/84-29 I. Introduction During a routine Nuclear Regulatory Commission (NRC) inspection of Sequoyah Nuclear Plant (SQN) surveillance activities in progress, j October 6 through Noveraber 5,1984, the NRC resident identified and J reported (reference 2) one violation and one potential reportable i occurrence which were addressed as three issues in the Stone & Webster Engineering Corporation (SWEC) systematic analysis, as follows:

(1) A02841214002-001 (Violation 327/84-29-01, 328-84-29-01), Failure to j establish adequate procedure for surveillance testing of Vital Battery Board.

1 (2) A02841214002-002 (Potential Reportable Occurrence 2-84-207)

Inadvertent Phase A Containment Isolation (3) A02841214002-003 (Violation 327/84-29-01, 328/84-29-01) Test f" personnel were not sufficiently familiar with surveillance 4

instruction.

A N:

II Verification of SWEC Issues L

S A. A02841214002-001, Failure to Establish Adecuate Procedure for e Surveillance Testing of Vital Batterv Board

1. Background 3 Appendix A of Regulatory Guide 1.3.3, Revision 2, February 1978, j'

Paragraph 8, requires that specific procedures for surveillance tests be established and implemented. The NRC inspector observed that adequate procedures were not established in that 7 Surveillance Instruction (SI) - 258.2 " Inspection of molded Case and Lower Voltage Circuit Breakers" failed to provide cautionary information in an appropriate manner to ensure maintenance of control power to diesel generator 2A-A during testing of breaker 213 on 125 VDC Vital Battery Board III. This resulted in an inadvertent auto start of all diesel generators when control power to diesel generator 2A-A was removed. Written procedures were not properly established or implemented, resulting in violation 50-327/84-29-01 and 328/84-29-01.

2. Corrective Actions Taken SQN stated (reference 2) that a temporary change was made to SI-258.2 to include the necessary steps to provide alternate l power when the breaker is being closed. SI-258.2 was submitted

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for permanent revision to include the necessary steps to provide alternate power when the breaker is being tested, and a signoff added to ensure that alternate power is provided to the fuse

column.

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3. Verification Methodology i'

^ The SWEC concern identified for Employee Concerns Task Group (EC1G) verification was stated as follows:

i.

RIMS # ISGUE RIMS ITEM

! A02841214002 Failure to establish adequate RIMS-001 procedure for surveillance resting of vital battery f

[ board resulted in inadequate

( start of all diesel generators.

. .ECTG reviewed th'e Sequoyah Compliance Licensing files for p internal and external correspondence related to this issue, the r

applicable procedure, and the NRC staty and tracking system for

, the issue. This review of the pertinent documentation formed b the basis for'this verification activity.

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[' 4. Verification Analysis k

(. The ECTG review indicated that the NRC violation was adequately

} resolved as follows: SI-258.2, " Inspection of Molded Case and T' Lower Voltage Circuit Breakers," was revised to provide alternate power to breaker 213 on the 125V Vital Battery Board-b- III when the breaker is being tested, and to include a signoff f

to ensure that the alternate power is provided to the fuse column. The corrective action was found acceptable to the NRC b' and the violation was closed in Report 85-26 i

( 5. Completion Status Based on SQN corrective action, compliance with requirements, and NRC closure of the item, no further actions on this item are

! required. This SWEC concern is closed.

g B. A02841214002-002 - Inadvertent Phase A Containment Isolation

1. Background f.

NRC investigated a potential reportable occurrence (PRO) ,84-207 concerning inadvertent phase A containment isolation, i

NRC found that the surveillance instruction in effect (SI-6,

" Containment Building Ventilation Isolation")-incorrectly stated l

in Revision 16, dated September, 1984, that manually initiating containment vent isolation while holding the phase A reset button would prevent a phase A isolation.

l 2. Corrective Action f

, SI-6 was promptly revised to prevent inadvertent phase A t

containment isolation during testing by lifting the leads to positively prevent, any phase A actuation signal. The revision also included requirements for independent verification for lead lifting and restoration during performance of SI-6.

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

RIMS # ISSUE R_ INS ITEM

! A02841214002 Inadvertent Phase A RIMS - 002 Containment Isolation during testing.

ECTG reviewed the applicable procedure (reference 3),

revision 17, for this item. This review of the pertinent documentation formed the basis for this verification activity.

4. Verification Analysis The ECTG review indicated that SQN took prompt corrective action

, to resolve the concern. The SI-6 revision was adequate to

, resolve this issue.

5. Completion Status Based on the verification activity above, ECTG considers the _

corrective action taken by SQN complete. The SWEC item can be closed.

C. 402841214002-003, Test Personnel Were Not Sufficiently Familiar with Surveillance Instruction

1. Background l The NRC inspector observed that test personnel involved in the l performance of Surveillance ~ Instruction SI-258.2, " Inspection of t

Molded Case and Lower Voltage Circuit Breakers," were not sufficiently familiar with the procsdure. This was included with NRC violation 327/84-29-01 and 328/84-29-01.

2. Corrective Actions ,

SQN stated (reference 2) that personnel were given additional guidance in the performance of this SI. The SI was successfully performed on October 24, 1984.

3. Verification Methodology The' SWEC conce,rn identified for ECTG verification was stated as follows:

s RIMS # ISSUE RIMS ITEM

, y A02841214002 Test personnel were not RIMS-OO3 sufficiently familiar with surveillance instruction for circuit breakers to prevent inadvertent start of diesel generator.. . ,

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4 ECTG reviewed the Sequoyah Compliance Licensing files for internal and external correspondence related to this issue, the applicable procedure, and the P!RC status and tracking system for the issue. This review of the pertinent documentation formed the basis for the is verification activity.

4. Verification Analysis The ECTG review indicated that the NRC violation was adequately resolved by reinstructing the test personnel. The corrective action was found acceptable to the NRC and the violation was closed in Report 85-26.

5. Completion Status Based on SON corrective action, compliance with requirements, and NRC closure of the item, no further actions on this item are required. This SWEC concern is closed.

III. References

1. NRC Repor ,0-327/84-29 and 50-328/84-29 dated December 12, 1984, David M. Verrelli to H. G. Parris

2. TVA Letter, Sequoyah Nuclear Plant - NRC-OIE Region II Inspection Report Numbers 50-327/84-29 and 50-328/84-29 Response to Violation dated January 18, 1985 (L44 850118 808)

3. TVA - SQN Surveillance Instruction SI-6, Containment Building Ventilation Isolation (18 month)

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