ML20207P629

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Rev 1 to TVA Comparison to Industry Medians
ML20207P629
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 01/05/1987
From: Gass K, Knightly J, Stewart D
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20207P454 List:
References
SWEC-SQN-12, SWEC-SQN-12-R01, SWEC-SQN-12-R1, NUDOCS 8701160338
Download: ML20207P629 (8)
v • d • e


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[ TVA EMPLOYEE CONCERNS REPORT NUMBER: SWEC-SQN-12

  • SPECIAL PROGRAM REPORT TYPE: Sequoyah Nuclear Plant Element REVISION NUMBER: 1 TITLE: TVA Comparison to Industry Medians REASON FOR REVISION: To incorporate TAS and SRP comments SWEC

SUMMARY

STATEMENT: The items in this report were identified by the Institute of Nuclear Power Operations (INPO) and were included in the Stone &

Webster Engineering Corporation (SWEC systematic analysis. All items ovaluated within this report were verified to be adequately addresssed with corrective action in progress.

PREPARATION PREPARED BY:

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

Title:

TVA Comparison To Industry Medians SWEC Concerns: A02841129011-002 A02841129011-005 -

A02841129011-010 A02841129011-011 A02841129011-012 A02841129011-013 A02841129011-014 Source Document: INPO Plant Performance Data, November, 1984 Report Number: SWEC-SQN-12 Evaluator: ty j (2-f4 %

- J. J. Knightly /- Date Reviewed By
Y /f b 2 1 /.d - V- 26 R.~ R. Gass Date Approved By: Md1w A. G. Debbag(

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.- Report SWEC-SQN INPO Plant Performance Data, 1984 I~.--Introduction In November 1984,.the Institute of Nuclear Power Operations (INPO) performed a review of TVA's plant performance compared with' industry medians (reference 1). -Several items from the review were addressed as issues in the Stone & Webster Engineering Corporation.(SWEC) systematic analysis, as follows:

1. A02841129011-002, SQN out'of service control room instruments exceeded the industry median.
2. A02841129011-005, SQN unplanned automatic scrams exceeded the

~ industry median.

3. _A02841129011-010, SQN Senior Reactor Operator (SRO) turnover rate

-exceeded the industry median.

T4. A02841129011-011, SQN forced outage rate exceeded the industry median

5. A02841129011-012 The number of actual design changes at SQN exceeded the industry median.
6. A02841129011-013, The number of temporary modifications installed at SQN exceeded the-industry median.
7. A02841129011-014 The number of Nuclear Performance Reliability Data System (NPRDS) failures at SQN exceeded the industry median.

II. Verification of SWEC Issues A. Background The INPO team compared TVA's operational data to other utilities ,

with the results as indicated in section II.C items 1 through 7.

B. Corrective Actions Taken

1. A02841129011-002. Control Room Instruments In 1984 Sequoyah's Instrument Maintenance Training Program l became the first craft training program in the industry to be l accredited by INPO. The SQN Nuclear Performance Plan (NPP), l Section II.4, describes the maintenance training and overall IR1 preventive maintenance program for achieving equipment l reliability. Additionally, section II.4.5 states that the l following startup activity will bo performed for plant l instrumentation: l Page 1 of 6

. Surval11cnce Instruction SI-604, "Esszntial Instrumentation l

. Operability Verification " will be performed by-the . 1 Instrument Maintenance Group to ensure that the essential lR1 surveillance instrumentation needed to monitor plant l-

. processes during' normal operating conditions is available I and operable. -

l 1

-2. A02841129011-005. Unplanned Automatic Scrams i

The SQN Standard Practice, SQA 129, " Objectives in Plant .I Operation-Sequoyah Nuclear Plant" established-October.1, 1986 a l goal of "less than or equal to three unplanned trips per unit," l Practices and policies to meet this goal include the following: l l

a. in-depth and thorough follow-up on all automatic scrams l I
b. identification of root causes of all automatic scrams l l
c. development of action plan to correct those root causes- <l and thereby to reduce the probability of future I automatic scrams l i

'The Operations Group supervisor and the Technical Support Group [R1 supervisor will review each trip report and investigate each l trip as needed to ensure the proper actions have been taken to l prevent recurrence. l 2

l

' The Performance Monitoring Unit shall prepare a monthly report l showing plant progress toward these objectives. t l

1 3. A02841129011-010 SRO Turnover Rate l l

Operations training personnel outlined for ECTG the following l steps that TVA has taken to reduce the SRO turnover rate: l l

Annually, a license maintenance bonus of $7,000 is l j paid to the SRO. l

l All SRO positions have been upgraded to the N-4 and '

l l M-5 management levels. l I

l The SRO positions have been placed in the highest of l

[ the three management pay brackets which are available l

for each TVA management grade. l

, I The SR0s are now permitted to leave shift work for l designated periods to serve in other plant capacities. l l

An Operations Training Manager stated to ECTG, "To my knowledge, l no SRO has left TVA in nearly two years." l

\

l '

Page 2 of 6 I

. 4. A02841129011-011. Ferced Outag* Rite The SQN NPP,Section II.4.3, establishes this objective for l plant maintenance relative to unit availability: l lR1 TVA and site management now recognize that plant maintenance l must become proactive and aggressive in its approach to .l evaluating and improving component and safety system performance l before long-term gains in safety system reliability, unit l availability, and reduction of maintenance-related errors can be l achieved. Achieving this long-term change in emphasis will l require that component deterioration be predicted and that SQN l initiates preventative actions before failures result. l l

A significant percentage of maintenance activities are routine l and, to a degree, repetitive. TVA's and Sequoyah's goal is to l control these activities through preplanning, us6 of in-house- l and industry experience, and increased trending. l Troubleshooting and corrective maintenance should be systematic. I so that root cause of failures are identified, and that l ,

technically sound solutions are developed'and implemented to l prevent recurrence. l 1

Selected nuclear maintenance objectives - including procedural i improvement, trending, training, management involvement, I improvement in work controls, root cause analysis, performance l monitoring, planning, and organizational improvements - are I addressed in the NPP,Section II.4, and in items -005, -013, l and -014 of this report. I l

5. A02841129011-012 Number of Design Changes l l

The SQN NPP,Section II.3.3 describos the action plan for TVA's l development of an improved design control program. A Change l Control Board (CCB) has been established to provide overall l control. Onsite DNE personnel are performing necessary reviews l to reduce interference problems, field changes, and design l errors. Frequent face-to-face meetings between those requesting l design changes and the design engineer is also improving the ,

l quality of design work. Centralizing responsibilities for l design changes has established greater accountability. TVA's 1

, goal is c design control system based on INPO Good Practice l Guidelines, with a single, stand-alone plant modification l package becoming the key document to maintain design control. l I

Page 3 of 6

_ ._ _~ _ - . - _. .

. ' 6i . LA02841129011 - 013. Numbir of Tempersey Medificatiens-The SQN NPP,Section II.1.2.8, describes corrective' actions to l

' improve the planning and scheduling of plant modifications, l noting that one-third of. approved modifications for unit 1 have .lR1

.later been cancelled.~ Corrective actions include: l

= . l Revision to the modification organization to place the 1 Planning and Scheduling section directly under the Site l Director l l

Preparation of. improved estimates and implementation plans l l

Incorporation of the engineering design phase of ~l modificatione into the site modification schedule l' I

  • - Stabilizing of Modifications work force  !

l Additional training for craft, engineer, and managers. l l

7. A02841129011 014. Number of NPRDS Failures l 1

The SQN Nuclear Performance Plan, section II.4 discusses the i emphasis now being placed on nuclear maintenance. Corrective l actions to improve reliability and reduce plant equipment I failures include the following: l l

_ Improvement-of maintenance procedures l l

Nore emphasis on trending activities to improve preventative l maintenance l l

Improved training of craft personnel l l

Greater management involvement l I

Improvements in work control systems l l

Improved program for employee performance reporting ,

1 C. Verification Nethodology The SWEC concerns identified for Employee Concerns Task Group (ECTG) verification were stated as follows:

RIMS NUMBER ISSUE RIMS ITEM A02841129011 Industry median 15 out of service RIMS-002 control room instruments. 1983 number for BFN 1 was 22. SQ1&2 similar.

t l

Page 4 of 6 f

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,, . 'A02841129011 . Industry medien fcr unplannsd RIMS-005

' 1 auto, reactor scrams = 4. BFN 2 = 11. SQN = 9.

A02841129011- Industry median for SRO turnover RIMS-010

=.0%. BFN = 28%. SQ = 15%.

A02841129011 Industry median 5.3% forced. outage- RIMS-011 rate. 1983 % for SQN = 18.1%.

9.68% for SQ2.

A02841129011 . Industry median 346 for active RIMS-012 design changes. SQ = 1591.

A02841129011 Industry median 37 for temp. RIMS-113 modifications-installed. 210 temporary modifications installed SQN.

A02841129011 Industry median = 59 NPRDS RIMS-014 failure reports 9 monthly 1984.

SQ1 = 280. 133 for SQ 2.

ECTG reviewed the INPO documentation on these concerns, SQN objectives and TVA's planned improvements as reported in the Corporate NPP (reference 3) and SQN Performance Plan (reference 4).

This documentation review formed the basis for this verification activity.

D. Verification Analysis The revised Corporate NPP and the revised SQN NPP provide an overall account of the actions which TVA is taking to improve its nuclear program for SQN. The planned implementation of improved programs in the areas of management, training, maintenance, design contro),

modificatione, quality assurance, and other areas is for the purpose of improving overall plant performance including all areas identified by the SWEC concerns.

E. Completion Status Adequate corrective actions have been initiated for the INPO items l identified in these SWEC concerns. The SWEC concerns are closed. lR1 with INPO follow-up review to be conducted after plant startup. l I

i Page 5 of 6 ,

e

, III. R-fe rn'* c's o-

1. INPO letter, "First Report of Plart Performance Data," dated November 27, 1984, Z. T. Pate to H. G. Parris
2. NRC letter, " Systematic Assessment of Licensee Performance -

Attachment 2, Sequoyah," dated September 17, 1985 W. J. Dircks to C. Dean

3. Tennessee Valley Authority Revised Corporate Nuclear Performance Plan, dated March 10, 1986
4. Tennessee Valley Authority, Revised Sequoyah Nuclear Performance Plan, dated July 17, 1986 l

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