Text

Forwards SALP Rept 50-395/88-32 for Aug 1987 - Dec 1988. Viewgraphs from 890328 Meeting Encl
	ML20245B036
Person / Time
Site:	Summer
Issue date:	05/18/1989
From:	Ebneter S; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Bradham O; SOUTH CAROLINA ELECTRIC & GAS CO.
Shared Package
ML20245B038	List: ML20245B036; ML20245B045;
References
	NUDOCS 8906220357
	Download: ML20245B036 (43)
	v • d • e

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Docket No. 50-395

License No. NPF-12

South Carolina Electric & Gas Company

ATTN: Mr. O. S. Bradham

.Vice President, Nuclear Operations

Virgil C. Summer Nuclear Station

P. O. Box 88

Jenkinsville, SC 29065

Gentlemen:

SUBJECT: SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE, REPORT

NO. 50-395/88-32

This refers to the NRC's Systematic Assessment of licensee Performance (SALP)

for your V. C. Summer facility which was sent- to you on March 17, 1989; our

meeting of March 28, 1989 at which we discussed the report; and your written

comments dated April 24, 1989.

We appreciate your efforts in evaluating the SALP report and providing

corrections and clarification to the Interim Report. I have enclosed a

summary of our presentation meeting, a copy of your written comments, a copy

of the slides which were used at the presentation, an errata sheet which

provides the basis for changes to the Interim SALP and the Final SALP report

for the period August 1, 1987 - December 31, 1988.

In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2,

Title 10, Code of Federal Regulations, a copy of this letter with the

referenced enclosures will be placed in the NRC's Public Document Room.

No reply to this letter is required; however, should you have any questions >

concerning these matters, I will be pleased to discuss them with you.

Sincerely,

w v0./ S N

Stewart D. Ebneter

Enclosurer.: (See page 2)

g622035789051s -

G ADOCK 05000395

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South Carolina Electric & Gas Company 2

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Enclosures:

1. SALP Presentation Meeting

Summary

2. Written Comments Received

from Licensee

3. Copy of SALP Presentation

Slides

4. Final SALP Report Errata

Sheet

5. Final SALP Report as Revised

from Interim Report

cc w/ encl:

J. L. Skolds, General Manager

Nuclear Plant Operations

A. R. Koon, Jr., Manager

Nuclear Licensing

J. B. Knotts, Jr.

Bishop, Cook, Purcell & Reynolds

W. A. Williams, Jr., Technical

Assistant, Nuclear Operations -

Santee Cooper

R. E. Rainear, Executive Vice

President, South Carolina Public

Service Authority

State of South Carolina

bcc w/encis:

Document Control Desk

L. W. Zech, Chairman

T. M. Roberts, Commissioner

K. M. Carr, Commissioner

K. C. Rogers, Commissioner

J. R. Curtiss, Commissioner

R. W. Borchardt, EDO

J. M. Taylor, DEDR

H. L. Thompson, Jr., DEDS

T. E. Murley, NRR

S. Varga, NRR

E. Adensam, NRR

J. J. Hayes, NRR

Regional Administrators, RI, RIII

RIV, and RV

R. Nease, SALP Coordinator, NRR

K. Clark, RII, PA0

D. Verrelli, DRP

R. Cart 011 DRP

K. Landis, Chief, TSS

P. Balmain, DRP

NRC Resident Inspector

DRS and DRSS Branch Chiefs,

and Section Chiefs

INP0

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j j UNITED STATE 5

NUCLEAR REGULATORY COMMISSION

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[f REGION 11

101 MARIETTA ST., N.W.

ATLANTA, GEORGIA 30323

MAY I 9 1989

Docket No. 50-395

License No. NPF-12

South Carolina Electric & Gas Company

ATTN: Mr. O. S. Bradham

Vice President, Nuclear Operations

Virgil C. Summer Nuclear Station

P. O. Box 88 ,

Jenkinsville, SC 29065 1

j

Gentlemen:

SUBJECT: SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE, REPORT

NO. 50-395/88-32 !

'

This refers to the NRC's Systematic Assessment of Licensee Performance (SALP)

for your V. C. Summer facility which was sent to you on March 17,1989; our

meeting of March 28, 1989 at which we discussed the report; and your written

comments dated April 24, 1989.

We appreciate your efforts in evaluating the SALP report and providing

corrections and clarification to the Interim Report. I have enclosed a

summary of cur.' presentation meeting, a copy of your written coments, a copy

of the slides which were used at the presentation, an errata sheet which

provides the basis for changes to the Interim SALP and the Final SALP report

for the period August 1, 1987 - December 31, 1988.

In accordance with Section 2.790 of the NRC's " Rules of Practice " Part 2,

Title 10. Code of Federal Regulations, a copy of this letter with the

referenced enclosures will be placed in the NRC's Public Document Room.

- No reply to this letter is required;. however, should you have any questions

concerning these matters. I will be pleased to discuss them with you.

-

Sincerely,

_ ,$

tewar D. Ebneter

i Regional Administrator

Enclosures: (See page 2) l '

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~ South' Carolina Electric & Gas. Company. 2

d. y 18' 1969

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-Enclosures:~ _

.

1.- SALP Presentation Meeting

Summary . .

2. Written Canments. Received

from Licensee-

3.- . Copy of SALP Presentation.

Slides

'4.- Final SALP Report Errata

at Sheet

'

5. Final SALP. Report'as Revised

from Interim Report

- cccw/encis: .

,

TJ. L. Skolds,' Genera 1' Manager

Nuclear: Plant Operations

.A. R.'Koon. Jr., Manager

'

NuclearLLicensing

J. B.'Knotts, Jr. . .

Bishop,' Cook,-Purcell & Reynolds

W. A.- Williams, Jr. ,' Technical

. Assistant, Nuclear Operations '-

Santee Cooper 1

'R. E. Rainear,-Executive Vice-

President,' South Carolina Public

Service Authority .

. State.of South Carolina,

,

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_ - _ - _ _ - - ___ - _-_-_-____ -__ _ _ _ _ . _ _ _ _ - _ - _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ . _ _ - _ - - - _ _ _ - _ _ _ _ - _ - - -

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ENCLOSURE 1

A. A meeting was held on March' 28, 1989 at the V. C. Summer site to discuss

the SALP report'for the period August 1, 1987 - December 31, 1988.

' B .' : Licensee Attendees.

SCE&G

John'A.. Warren Chairman & CEO, Scana

Lawrence M. Gressette President, Scana

Thomas C. Nichols, Jr. President &'CEO, SCE&G

Osmond W. Dixon, Jr. Executive Vice President, Operations

Dan A.'Nauman Senior Vice President, Power Production

Ollie S..Bradham Vice President, Nuclear Operation

John L. Skolds General Manager, Nuclear Plant Operation

Michael B. Williams General Manager, Nuclear Services

David R. Moore General Manager, Engineering Services

Ken W.. Nettles General Manager, Nuclear _ Safety-

Gene-G. South General. Manager; Operations &

Maintenance

Santee Cooper

William Mescher President & Chief Executive Officer

R. E. Rainear Executive Vice President- 4

'W. A. Williams Techical Assistant, Nuclear Operations

C. NRC Attendees

S. D. Ebneter, Regional Administrator, Region II (RII)

C. W. Hehl, Deputy Director, Division-of Reactor Projects (DRP), RII

F.-S. Cantrell, Chief, Section 18, DRP, RII

L. P. Modenos, Project Engineer, Section 1B, DRP, RII

E. A. Reeves, Acting Director, Project Directorate II-1. NRR

J.'J. Hayes, Jr., Senior Project Manager, NRR

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April 24, 1989 3.~

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Mr. S. D. Ebneter l

Regional Administrator

U. S. Nuclear Regulatory Commission

Region II, Suite 2900

101 Marietta Street, N.W.

Atlanta, Georgia 30323

-

Subject: Virgil C. Summer Nuclear Station

Docket No. 50/395

Operating License No. NPF-12

NRC Inspection Report 88-32

Licensee Comments

.

Dear Mr. Ebneter:

The following comments are being submitted in accordance with your letter

dated March 17, 1989:

1. Page 4, last paragraph, fourth sentence.

South Carolina Electric & Gas Company

where procedures with known errors were(SCE&G) required toknows of no

be used. specific case

When

problems were identified with procedures, actions were taken to correct

the problem Use of procedures with known errors has not been, nor is it

now, an acceptable practice.

2. Page 8, fourth paragraph.

It is SCE&G's intent, and has always been its philosophy, to operate the

plant by the consistent use of accurate procedures. The mistakes

identified during the review period have been investigated and

determined to not be technically significant. However, Operations will

perform a walk-down of all safety related system lineups and correct any

errors discovered between system operating procedures, surveillance

-

procedures CHAMPS nomenclature, and controlled systems drawings. This

)

will require an extensive manpower effort to oe continued through the

next SALP period.

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Mr. S. 0. Ebneter

April 24, 1989

Page 2' .

3. Page 15, third paragraph, fourth sentence.

High quality maintenance is considered to be essential in order to

maintain the plant in-the best possible state based on resources

'available. A perceived weakness was: addressed.in the excessive time

required to perform specific functions supported by the vendor. It is a

normal process to use vendor estimates in developing an outage schedule.

The vendor underestimated the difficulty in our process and SCE&G also

experienced equipment malfunctions. The final observation, a lack of

line supervisor involvement, is a concern for maintenance management.

SCE&G has expressly encouraged the " supervision in the field" philosophy

and believes that it is paramount to getting the , job done right the

first time.

'

SCE&G will continue to stress this issue and remove the

actual stumbling blocks that prevent this from happening.

4. Page 21, third paragraph, last sentence.

The number'of Design Base Documents (08D's) to be developed is

approximately 40 instead of 50.

5. Page 22 third paragraph, last sentence.

The apparent weakness is in "getting the issue into the modification

stage" and not in " engineering support."

6. Page 26. first paragraph, second sentence.

.

The second example described in this sentence relates to SCE&G's

submittal for L*. The following.is a more accurate description of the

L* criteria than that provided in the draft report.

1) the defects are located more than .5 inch into tha tubesheet,

.

2) the defects are oriented not greater than 30' from axial, and

3) a minimum of 1.3 inches of sound expanded tube exists in the top

portion of the affected tube.

.

_ _ _ _ _ _ . _ _ _ _ . . _ - - - - - - - - - - - - - - - - - - - --

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Mr. S. D. Ebneter !

April'24, 1989 -

Page 3

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7. Page 27. second paragraph, second sentence.

t On September 29, 1988, SCE&G provided the initial response to NRCB 88-

08. Prior to making the submittal, SCE&G requested a meeting with the

.

NRC to discuss the proposed SCE&G plan for implementing the requirements

of NRCB 88-08. On October 6, 1988,'a meeting was held to explain in

detail the methodology used to arrive at the proposed plan. At the

meeting the NRC staff determined the program was acceptable for the

present refueling outage; however, they requested that SCE&G submit

additional information prior to restart. This submittal was made by

SCE&G on December 19, 1988 (plant startup-December 29,1988).

Therefore, submittals pertaining to this bulletin were made within the

requested time frames. The meeting held on October 6, 1988, was

requested by SCE&G to fully explain the methodology used to address the

bulletin requirements in an attempt to decrease the required effort and

review time by the NRC. Every effort was made by SCE&G to reduce NRC

staff effort necessary to obtain an acceptable program to address NRC

Bulletin 88-08.

Should you have any questions, please call us at your convenience.

Very truly yours.

O. S. Bradham

EE/OSB: led

.

c: D. A. Nauman/0. W. Dixon, Jr./T. C. Nichols, Jr.

E. C. Roberts

W. A. Williams, Jr.

General Managers

J. J. Hayes, Jr.

C. A. Price /R. M. Campbell, Jr.

R. B. Clary

J. R. Proper

K. E. Nedland

J. C. Snelson

G. 0. Percival

l R. L. Prevatte

l J. B. Knotts, Jr.

Marsh & McLennan

Document Management Branch

INP0 Records Center

ANI Library

NSRC l

NPCF q

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RTS j

(IE883200)

File (815.01)

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ENCLOSURE 3

EXITED STA" ids

XECLEAR REGULATORY

.

COMMISSION

.

SYSTEMATIC ASSESSMEXT

0F '

LICEXSEE PERFORMANCE

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SOETH CAR 0mIXA

ELECTRIC AND GAS

COMPAXY

A GL ST ' , ' 987 : 1roug1 DECEMBER 31, 1988

V.C.SJVVH

VARC- 28, ' 989

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_ _ - _ - - - - - - - - .

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SALP PROGRAM OBJECTIVES .

.

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)E\"M "REs JS \ _'CEsSEE 3 err 0RVA\CE

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2. 3 ROV J E A 3AS S

70 R A__0CA"'O \' i

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RESOJRCES

3. V3 ROVE \ RC

REGUXORY. 3ROGRAV

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4

REGIONIIORGANIEL ON

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ADMMISTRATOR S. ENETUt

DEPUTY M. DBtST

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STAFF

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DIVISION OF REACTOR PRC 2 CTS

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ORGANIZATION

ommon or

REACTOR PROJECTS

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olR. .L REYES our K. uses

DEPUTY C.HDR.

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REACTOR PROJECTS REACTOR PROJECTS REACTOR PROJECTS

BRANCH N0. 1 BRANCH N0. 2 BRANCH N0. 3

CHIEF D. VERRELU CHIEF B. WILSON CHIEF A. HERDT

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NRR ORGANIZATION

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NUCLEAR REACTOR

REGULATION

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DR. THOMAS E. WURLEy & Alu p as s w r

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ASSOC. DIRECTOR ASSOC. DIRECTOR FOR

FOR PROJECTS

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TECHNICAL ASSESSMENT

DIV. OF DIONGUNG

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WAJOR CHANGES T0 "hE !

SALP PROGRAM CONSIS" 0F...

Redefinition of Functional Areas

Reduction in Number of Separate

Functional Areas

Two New Functional Areas

Engineering / Technical Ssupport

Safety Assessment / Quality Verification

Attributes Addressing Human Performance ,

and Self- Assessment

Emphasis on Analysis

_ _- _ _ ---

. .

JNC"OYA_ AREAS

03 ERAT NG REACTORS

Plant Operations .

Radiological Controls

Maintenance / Surveillance

Emergency Preparedness .

Security .

Engineering / Technical Support

Safety Assessment / Quality Verification

Other

.

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ENG NEERING/TECHNICA_SLPPORT

.

The purpose of this functional area

is to address th'e adequacy of technical

and engineering support for all plant

activities. It includes all Licensee

Activities associated with the design -

'

of plant modifications; engineering and

technical support for operations, outages,.

maintenance, testing, surveillance; and

rocurement activities; training; and

configuration management (including

maintaining design bases and safety margins).

.

,J

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SAFETY ASSESSMENT /QUAUTY VERIFICATION

The purpose of this functional area is to address the

technical adequocy and completeness of the licensee's

approach toward a variety of activities associated with

the implementation of licensee safety policies and

licensee activities related to amendment requests, exemption

requests, relief requests, response to generic letters,

bulletins, and information notices, and resolution of TMI

items and other regulatory initiatives. It also includes

licensee activities related to the resolution of safety

issues,10 CFR 50.59 reviews,10 CFR 21 assessments, safety

committee and self-assessment activities, analysis of

industry's operational experience, root cause analyses of

plant events, use of feedback from plant quality assurance /

quality control (QA/QC) reviews, and participation in self-

improvement programs, it includes the effectiveness of the

licensee's quality verification function in identifying

substandard or onomalous performance in monitoring the

ovsroll performance of the plant.

.

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3ER Ch AsCE RA" sG CA"EGOR ES

.

Expanded d"scuss on intent

Redefinition of the categories to clarify

~

the"r mean"ng

.

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,, ..-

PERFORMANCE AXALYSIS AREAS

FOR OPERATING REACTORS

.

1. PLANT OPERATIONS

.

2. RADIOLOGICAL CONTROLS

3. MAINTENANCE / SURVEILLANCE

, 4. EMERGENCY PREPAREDNESS

5. SECURIT(

6. ENGINEERING / TECHNICAL SUPPORT

7. SAFET( ASSESSMENT / QUALITY VERIFICATION

i

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AREA PERFORMANCE

C/TEGORY 1

!

UCENSEE MANAGEMENT ATTENTION AND INVOLVEMENT

ARE READILY EVIDENT AND PLACE EMPHASIS ON SUP

PERFORMANCE OF NUCLEAR SAFETY OR SAFEGUARDS

ACTMT1ES WITH THE RESULTING PERFORMANCE SUB -

STANTIALLY EXCEEDING REGULATORY REQUIREMENTS.

UCENSEE RESOURCES ARE AMPLE AND EFFECTIVELY U

S0 THAT A HIGH LEVEL 0F PLANT AND PERSONNEL

PERFORMANCE IS BEING ACHIEVED. REDUCED NRC AT

MAY BE APPROPRIATE.

- - -

. ..

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AREA PERFORMANCE -

C/TEGORY2

UCENSEE MANAGEMENT ATTENTION TO AND INVOLV

IN THE PERFORMANCE OF NUCLEAR SAFETY ~0R S

ACTMTIES ARE GOOD. THE UCENSEE HAS ATTAINED

LEVEL 0F PERFORMANCE AB0VE THAT NEEDED TO ME

REGULATORY REQUIREMENTS. UCENSEE RESOURCES A

ADEQUATE AND REASONABLY ALLOCATED S0 THAT G

AND PERSONNEL PERFORMANCE IS BEING ACHIEVED.

i

ATTENTION MAY BE MAINTAINED AT NORMAL LEVELS.

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AREA PERFORMANCE

i

C/TEGORY 3

UCENSEE MANAGEMENT ATTENTION TO AND INVOLVEM

IN THE PERFORMANCE OF NUCLEAR SAFETY OR SAF

ACTMTIES ARE NOT SUFFICIENT. THE UCENSEE'S

PERFORMANCE DOES NOT SIGNIFICANTLY EXCEED T

TO MEET MINIMAL REGULATORY REQUIREMENTS. UCEN

,

RESOURCES APPEAR TO BE STRAINED OR NOT EFFE

USED. NRC ATTENTION SHOULD BE INCREASED ABO

l

LEVELS. !

_ _ _ --- ---- ---_

.. ..

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EVAILATION CRITERIA

1. MANAGEMENT INVOLVEMENT IN ASSURING QUAUTY

2. APPROACH TO RESOLUTION OF TECHNICAL ISSUES

FROM A SAFETY STANDPOINT

3. RESPONSNENESS TO NRC INITIATNES

4. ENFORCEMENT HISTORY

.

5. REPORTING AND ANALYSIS OF REPORTABLE EVENTS

6. STAFFING [lNCLUDING MANAGEMENT)

.

7. TRAlf!lUG EFFECTIVENESS AND QUAUFICATION

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V CE ON SUMMARY

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AUGUST 1,1987 through DECEMBER 31,1988

I ll lil IV V '

V. C. SUMMER 0 0 1 14 4

REGION ll AVE. 0 0 2 19 5

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PER UNIT

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AUGUST 1,1988 through DECDRER.31,1988

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LEGEND

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EEi PERSONNEL (other) = 1 ,

" "

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FERSONNEL (test / col) = 5

h PERSONNEL (maintenance) =

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OTHER = 3

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V. C. SEMMER;IiERs

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51.9%

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DESIGN /CONST.

COMP. FAILURE

_ _ _ _ _ - _ - _ _ _ _ - _ - _ _ _ - _

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(PERSONNEL)'

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TEST /CAUB.

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OTHER

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OPERATIONS

42.9%

i

\

_ - _ _ _ - _ _ _ _ _ _ - _ _ _ - - _ _ _ -

-

.. ..

t-

~

7

.

. 0NCTONA_ AREACOV?AISON .

..=OR R W CN I

=ACl ?ES

CYC_EV

f4 -

7 LEGEND

" Ed CATEGORY 1

'

Wd CATEGOR

, ,, ..

S b ,

CATEGORY 3 ,

0

' t

,.

.

-

- '

.

a, - =

,

gg' ..

-

.

,

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'

I

4" i

-

2-

, il . .

1 . . .

OPS

MAINT EM PREP

RAD CON SURV RRE PROT

FUNCTIONAL AREA

_-______.

- .

..

2. <

!

..- ?

NCTONA_ AEA COV? ARSON

..?OR REG l0N

FAC_~ES

CYC_E V

LEGEND

E CATEGOR

;

[M/ CATEGO

-

CATEGORf 3

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SEC OU1 E S QP UC MG WGR SUP

FUNCTIONAL AREA

_ _ _ _ - - - _ _ - - - -

-

. . .

...

'bI

,.

L

.

'

-

PIM OPERATIONS - CATEGORY 2

o. CORPORATE OVERSIGHT EVIDENT FR0W FREQUD

PLANT TOURS By SENIOR MANAGEMENT

\

o OPERATIONS GROUP IS WELL STAFFED AND EXPERI

NEGUGIBLE TURNOVER

o EFFECINE OPERATOR RESPONSE TO OFF-NORMAL C

AND PLANT TRANSENTS .

. -

'

o CONTROL R00W PROFEssiONAUSW WAS RWINELY

.

. o PUNT HOUSEKEEPING CONSIDERED AVERAGE : ,:e'

.

o REACTOR 1 RIPS DURING LAST TWO SALP PERIODS

EXCEED NDUSTRY AVERAGE

o WEAKNESS DENTHD N PROCEDURE ACCURACY AN

o COMPENSATORY WEASURES FOR DEGRADED FIRE BA

4

NOPERABLE FRE EQUIPMENT NEEDED NPROVEMENT

'

(

'.

-

. . . . .

. .

, , .,

.

.... ..

g

..

RADIOLOGICAL CONTROLS - CATE

..

o MANAGDENT SUPPORT #5 BWOLVDENT

RADIATION PROTECTION WERE DSENT -

o KNOWLEDGE AND EXPERIENCE 11 vel.

.

. WERE EX@lFNT

..

o

CONTAMINATED AREA 0F PLM WAS LES

TOTAL AREA M.ONITORED

,, ......

..

o

RESPIRATORY PROTECil0N k AND RWP.P$4

..

. .o

SPlKED SAMPlf ANALYSIS SHOWED AGR

. o

UCENSEE AUDRS AND SURVEWWCES WERE

o

'

CollECTNE DOSE AND NUMBER OF PERSl l

NEED CONTNUED ATTENT10N

i

- _ _ _ _ _ _ - - _ _ _ _ - _ _ _ _ _ _ _ - - _ _ - _ _ _ - _ _ - - - _ _ _ - _ _ _ _

.. ..

t

!

,

MAINTENANCE / SURVEILLANCE - CATEGORY 1

o

MAINTENANCE ORGANIZATION IS ADEQUATELY STAFF

TRAINED TO SUPPORT OPERATION OF THE PLANT i

o

-

PREDICTIVE MAINTENANCE PROGRAM EFFECINE

.

,

o

LOW WWR BACKLOG WITH RELATNELY FEW OLDER THA

~

MONTHS

o

WEAKNESS IN THE FIRST-UNE SUPERhSO

WORK PLANNING ACTMTIES .

o

HIGH NUMBER OF TRIPS DURING THE PERFORMANCE OF

SURVEILLANCE TESTS

.

-

.. ..

a

. .

.

. .

.

.. .

.

. . .....

..

...

....

.

, . .. .. .....

.

...

. .

.. -

.

. .

.

%

._

. .... .

.

-

,

-

1

. . ... .... .. . !

.

. ..

,

. .

.

'

I

8

l 0

.

. , .

-

EMERGENCY PREPAREDNESS - CATEG 1

..

.

i

o OVERAll. @UTY TO MEQUATELY WPL.E

. ..

.. . ..

. .. ..

'

.

OF"THE 5.lERGENCY PLAN DEM. ONh.l6IED

.

. .

.

?l .g71 -

i

o AN EFFECTIVE S:

. . . .. . .

.

M6N60EMENT AND CON

. *

5

.

. . .

N&.. .

F

-

'

o ERF APPRelS6L ....

.

DETERM!NED FACUTIES M -

o W#NE.SS NOTED N EVENT CLASSIFICATION

. .. .

.

4

I

'

.

,

o .RECllRRENT PRO.BLE.M. N TH.E. AREA 0

.. . . . . .

,,

.

e

.

- - - - - -

-

...

.

-

.

SECURl1Y- CATEGORY 2 DECUNING TRENI

o

EXTENSNE RESOURCES EXPENDED N UPGRADI

HARDWARE

~

o

SERIOUS DEGRADATION OF PROGRAM OCCURED

"

Half 0F SALP PERIOD -

'

.. . . . . -

,

o

.. MANAGEMENT SLOW IN RECOGNIZING SITUATI

CAUSED DETERIORATING SECURITY WOR 4LE

..

-

o

CRITICAL SELF-ASSESSMENT WAS LACKING W '

EARLY IDENTIFICATION OF PROBLEMS

~

l

o 1

SIGNIFICANT MANAGEMENT ATTENTION NEEDED 1

l

_ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ - _ - - - - _ - - . - - - - - - -

.

. ..

a

.

ENGINEERING / TECHNICAL SUPPORT - CATEGO

-

o

NmATED OR CONTINUED SEVERAL WMOR EFFORTS TO lWP

OR WAINTAIN QUAUTY OF ENQNEERING PERFORMANCE '

o

ENGINEERING PERFORMANCE ON SPECIFIC TECHNICA

BEEN 0000 t

.

o

'

MODIFICATION BACKLOG REDUCED -

o

CONTINUED EFFORT ON SAFEiY SYSTEW bNCT1

'

o

PROCUREMENT PROGRAW CONSIDERED.A SfRENGTH

o

WANAGEMENT COWWl1 MENT TO SUPPORT EQ DHNCEMEN

AND TO RESOLVE NRC CONCERNS AND NmATNES N A TMl

WANNER NO B

i

.

o

IMPROVEMENTS NOTED IN A TRAINING PROGRAWS AND FACluTI

HOWEVER A SHORTAGE OF INSTRUCTORS NOTED

l

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - - - - -

,. ,

, ..

.

27

.

..:

i

j

.

,

'

i

SAETY ASSESSMNI/QLUUTY NTM - CA

o OPERATIONS, ENGNEERNG, AND MANAGEMENT NVOLVE

WAS APPARENT N PUNT SAFETY REEWS

- .

.

o

ISEG PROVIDED W-DEPTH REVIEWS OF PLA

"

SARlY CONCERNS.

.

, . . ,

,

.

, ,,. . .

..

p

-

.

o .

FORMATION OF OPERATNG EXPERIENCE G

OVERSIGHT AREA HAS NPROVED 11MEUNESSy RESOL

ISSUES

.

_ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _

.

.. ..

2r

[

.

'

l

.

o

TREND TOWARDS PERFORMANCE BASED QA REMEW H

o

'

PRIOR PLANNING AND AGGRESSIVE ACTION TO RE

PROBLEWS EVIDENT

l

.

o

RESPONSE TO NRC BULLETINS AND GENERIC LUTERS W

-

USUALLY TIMELY AND COMPLETE

.

. .

.

o ADEQUACf 0F REVIEW 0F CONTRACTOR SUBWITTAL

-

.

o

SOME OCCASIONS WHEN LACK OF QUAUTY CONTROL IN

SUBWITTALS NECESSITATED AD0m0NAL SUBWITTALS

,

9

- - - _ _ _ - _ _ - _ - _ _ _ - -

, -

.

. .

... ..

et

.

.. .

... .,. ..:,-

-

.

. . , n., -

. . , . .:.

. .

-

. '

....

. . ::-

.-

...

. .

.

SUMMARY OF RESULTS

.

'

o

OVERAll, PUNT WAS OPERATED M A SAFE MANNE

... .

o ..

CORPORA

APPARENT '

1E INit.xEst AND DVERSIGH

.-

- -

.

..

. .

. . , ,

o

OPERATIONS PE.RFORMANCE .

. . .-

WAS WlXED

-

. .. ,.

.. .

-

. o _

.

CONTINUED MANAGEMENT ATTENTION .

. . .. .

ROOT CAUSE AND ACHIEVE TRIP REDUCT

.

. .. . .

o

i FIRE PROTECTION AREA Will REQUIR

i

.

TO PREVENT REri;HiiVE PERFORMANCE PROBLEW

o

RA'Dl0 LOGICAL CONTROLS ARE l

.

_ _ _ _ _ _ ~ ~ ~ - - -

. . - - - _ _ ---

.

..

se

.

.e +

o

...

.

..

.

-

. .

.

o WANTENANCE/SURV8tDHCE

. .

.

. . . . ,. ,. .

. w+:s- , . .. ~ PR

. .

. ma.e .- . . -

o EMERGENCY PREPAREDNESS AC1hEES

W DENif1ED M 1RA,I.NH. G 0F KEY ..:

.

AND PROMPTLY IENTFYNG, CLASSFYNG

EVENTS ,

.

... *..

.

'-. o SECURITY AREA EXPEiaENCED,SEVERA

LATE...N E*fasWT PERIOD .-

.

.. g: .

oEhW DIGNMNG/

PERIOD TECHNICAL SUPPO

.

-

o

SAFETY E%5erWr/QUALHY VERI

WAS.. GOOD

.

4

W4

_ - _ _ - _ _ _ _ _

_ , . , 'A*

I

,

L

ENCLOSURE 4

I

ERRATA SHEET

Page Line Interim Report Reads Final Report Now Peads

'

4 45-47 ... procedures with known ... procedures containing

errors and the. . . drawings, errors, the..., and the

L and acceptable system lack of acceptable

system

8- 50-51 It was anticipated that Operators had to

operators.would make... make...

Basis: Revised to reflect staff finding that procedures were revised and

approved for use without adequate review. Operators were required to

make corrections during system alignment.

15 15-29 (Third paragraph revised in its entirety)

Basis: Revised to clarify the lack of adequate estimates for outage work

which resulted in exceeding time allotted.

21 28 ...approximately 50 DBDs ...approximately 40 DBDs

Basis: Revised to correct the number of Design Basis documents to be developed.

22 28 ...in engineering support... ...in modifications control...

Basis: Revised to correct identified weakness as modifications control

instead of engineering support.

26 6-8 ...which would allow a ...which established

circumferential crack in a the tube sheet region alternate

-

steam generator tube within plugging (L*) criteria for steam

0.5 inch of the tube sheet generators at the Summer station,

with the cracked tube being

plugged.

Basis: Revised to more accurately describe L* criteria.

- _ _ _ _ - - _ _ _ - _ _ _ _ . _ _ _ _ _

. - - _ . -

)g . .-.

l. - Enclosure 4

. 2

Pg Line- Interim Report Reads Final Report Reads

.;

r- 27 6 ...two exceptions were the... ...one exception was the...

27- 9-10 ... setting, "and Bulletin ... setting". This submittal.

88-08" Thermal Stresses in

i

'

.in piping connected to Reactor

Coolant System."

l. These submittals...

.

27 11 ...obtain acceptable... ...obtain an acceptable...

Basis: Revised to delete Bulletin 88-08 as an example of untimely licensee

response.

.

m__ _ __ __m.m.__.__-_____.____m. _ . _ _ _ _ . - _ _ _ _ . _ . _ . -

_._-.m_ , - . . . . _ - _ _ _ . _ . . _ _ _

-

ML20245B036

Text

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