ML20235R478
| ML20235R478 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 08/15/1988 |
| From: | Collins S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Russell W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20235R314 | List:
|
| References | |
| FOIA-88-519 NUDOCS 8903030320 | |
| Download: ML20235R478 (52) | |
Text
Q4 UNITED STATES s
-j
- NUCLEAR REGULATORY COMMISSION j
_.j REGION I 475 ALLENDALE ROAD i
KING OF PRUSSIA. PENNSYLVANIA A 194o6 AUG i 91988 MEMORANDUM FOR: William T. Russell Regional Administrator FROM:
Samuel J. Collins, Deputy Director
. Division of Reactor Projects
SUBJECT:
PILGRIM RESTART ASSESSMENT PANEL MEETING MINUTES On August 11 1988,- the Pilgrim Restart Assessment Panel met by teleconference to discuss the status of NRC and licensee activities associated with'the pro-posed plant restart. The following personnel.were in attendance:
Chairman:
' Samuel J.
Collins, Deputy Director, Division of Reactor Projects (DRP)
Members:
James T. Wiggins,. Chief, Reactor Projects Branch No. 3, DRP' Jacque P.
Durr, Chief, Engineering Branch, Division of' Reactor Safety (DRS)
William J. Lazarus, Emergency Preparedness Section, Division of Radiation Safety and Safeguards (DRSS)
Others:
Clay C. Warren, Senior Resident Inspector The panel discussed the issues from the last meeting, as well as the overall integration of NRC inspection and review activities. As a result of the meet-ing, the below listed actions with responsibility were agreed upon by the Panel.
A panel meeting will be held at the Sheraton in Plymouth, August 25, 1988, at 2:00 p.m.
Panel members are encouraged to be present since a phone bridge may not be-available for this meeting.
All items below will be updated..No separate agenda will be provided for the Augu t 25 meeting.
Task Responsibility Due Date 1.
Plant Status Update Resident Inspector Next Panel 2.
Staffing / Organization Update Resident Inspector Next Panel Training Manager Maintenance Training 3.
Site Inspection Activities Resident Inspector Next Panel Update PDR
/S,
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AUS 151988 e
, Memorandum for William T.' Russell 2
L 1
Task' Responsibility
'Due Date 4
Update fire barrier issue.
Boger/Blough Next Panel
. status of BECo submittal 5.
Review and update NRC Restart All Next-Panel i
checkli st 6.
Provide OIL' Updates All Next Panel 7.
ACRS Sub-Committee Preparation Collins Next Panel Status 8.
Restart Assessment Report --
All Next Panel i
Begin work IAW assignments -
discuss each panel
'9.
Update Overall Milestone-Cc111ns Next Panel Schedule
- 10. Update Subset Milestone Ai!
Ongoing Schedules Update EP Subset Bellamy Next Panel Provide comments ~to Mcdonald Next Panel 2.206 Subset
- 11. Update Status of Power Durr Next Panel Ascension Program Deficiencies
- 12. SEP Issues Status Boger Next Panel
.14.
Degraded Security Condition -
Wiggins Next Panel Enforcement Approach
~~
' 15'.
Wiggins Next Panel Enforcement Approach
- 16. Emergency Preparedness Status Bellamy Next Panel amue v.
o ins, Deputy Director Division of Reactor Projects I
= _ _.
1 w.
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.e Memorandum'for William T. Russell 3-AUG 151988 Enclosuress 1.
Pilgrim Overall Milestone Schedule, Revision 10 l
- 2.
Pilgrim Subset. Milestone 2.206 Approach, Revision 3
~
3,
. Pilgrim.' Subset Milestone Topic Listing, Revision 9 a
L cc w/encis:
T. Murley, NRR
'F. Miraglia, NRR T. Martin,.NRR S.iVarga; NRR B. Boger,~NRR R. Wessman, NRR l
D. Mcdonald, NRR i
i F.'Akstulewicz, NRR J. Roe,:NRR J. Hannon, NRR-W. Regan, NRR P. Stohr, NRR B. Clayton,:EDO J. Allan, RI W. Kane, RI S. Collins, RI J. Wiggins, RI-R. Blough, RI S. Ebneter, RI
' J. Durr,-RI R. Bellamy, RI L. Doerflein, RI M. Kohl, RI C.. Warren, SRI - Pilgrim J.'Lyash, RI - Pilgrim
..T.-Kim, RI - Pilgrim i
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ENCLOSURE 3 Subset Milestones Topic Listing Area Responsibility A.
Overall Milestones S. Collins B.
Public and State Involvement R. Blough Meetings with Licensee C.
NRR Actions for Restart D. Mcdonald D.
Management Transition C. Warren E.
Site Inspections / Reviews R. Blough F.
EP Status R. Bellamy/F. Congel G.
Power Ascension Program J. Durr H.
2.206. Item Closecut Approach R. Wessman l
S. Collins Pilgrim Subset Milestones 8/12/88 l
Rev. 9 1
____..-____-__-__.-___-_-__-m_
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- SLIDE 1 UNITED STATES NUCLEAR REGULATORY COMMISSION
' ADVISORY COMMITTEELON ' REACTOR SAFEGUARDS g
TECHNICAL' MEETING'- AUGUST-26, 1988.
REVIEW OF-PILGRIM NUCLEAR (POWER STATION-RESTART' ACTIVITIES MEMORIAL HALL 83 COURT STREET PLYMOUTH, MASSACHUSETTS SAMUEL.J. COLLINS
- ~
DEPUTY' DIRECTOR, DIVISION l0F REACTOR-
-PROJECTS,-REGION'l FTS, 346-5126 i
7 I*'
- 11.
[4RC STAFFLPRESENTATIONS SLIDE 2-l
~4GENDA l
I I '.
NRC STAFF PRESENTATIONS-A.
If4TRODUCT10N -
L
.B.
HISTORICAL PERSPECTIVE-ISSUES 1.
- ISSUES LEADING TO APRIL'1986 SHUTDOWN
-2.
APRIL 1986 SHUTDOWN, CONFIRMATORY ACTION
' LETTER (CAL)-(86-10)'
3.
. NOVEMBER 1986' MANAGEMENT MEETING (86-41)'
4.
'SALP' FINDINGS (86-99) 5.
OTHER ISSUES l
i
. I J
a
a a
u*i, j
b Y~. ?
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.ll. A.:
INTRODUCTION-SLIDE'3:
INTRODUCTION 0F NRC STAFFJ o
. SAMUEL J. COLLINS,' DEPUTY: DIRECTOR,. DIVISION
.0FLREACTOR PROJECTS, REGION-1, o
ALLEN R. BLOUGH, CHIEF,' REACTOR PROJECTS SECT 10N.3B, DRP l
o L'AWRENCE T. DOERFLEIN, PROJECT ENGINEER,.RPS 3B o
BRUCE A. B0GER,' ASSISTANT DIRECTOR FOR REG 10N 1 REACTORS,:0FFICE OF. NUCLEAR REACTOR-REGULATION ~
.o DANIEL G -MCDONALD, LICENSING PROJECT MANAGER, NRR o
I O
L ll.B.
HISTORICAL PERSPECTIVE SLIDE 4
~
ISSUES PURPOSE:
o TO PROVIDE. BACKGROUND'AND HISTORY OF ISSUES AT PILGRIM NUCLEAR POWER STATION IN ORDER TO PLACE. PERSPECTIVE ON NUCLEAR REGULATORY COMMISSION (NRC).AND BOSTON EDISON COMPANY
. BECO). ACTIONS IN REGARDS T0 RESTART ACTIVITIES.
(
CONTEXT:
o A REVIEW 0F PAST 1SSUES TO PROVIDE H1STORICAL.
.-BACKGROUND.
o-ISSUES' PRESENTED HAVE BEEN THE SUBJECT 0F BECO CORRECTIVE ACTIONS AND NRC STAFF
-VERIFICATION ACTIVITIES.
.o ISSUE RESPONSE BY BECO AND VERIFICATION BY NRC WILL'BE ADDRESSED IN SUBSEQUENT PRESENTATIONS.
i I
=_N__._--=_---____..-_-____.
. --- __ __ _b
f 12,. B.
HISTORICAL PERSPECTIVE SLIOE b
~
BACKGROUND INFORMATION ON PILGRIM NUEEAR PONER PLANT-Utility:
Boston Edison
. Location:
4 Mi SE of Plymouth,, Massachusetts County:
Plymouth County, Massachusetts Docket No.:
50-293 CP 1ssued:
8/26/68 Dperating License 1ssued:
9/15/72 Initial Criticality:
6/16/72 (Based on a 20% power license issued 6/9/72)
Elec. Ener. Ist Gener:
7/29/72 Commercial Operation:
12/1/72 Reactor Type:
BWR 3/4 Containment GE MKI Power Level:
670 MWe; 1998 MWt Architect / Engineer:
Bechtel NSSS Vender:
General Electric Constructor:
Bechtel Turbine. Supplier:
General Electric Condenser Cooling Method:
Once Thru Condenser Cooling Water:
Cape Cod Bay Licensing Project Mar.ager:
Daniel G. McDcnaid (Telephone: 492-3436)
NRC Responsible Region:
Region I, King of Prussia, Pennsylvania William T. Russell, Regional Administrator James M. Allan, Deputy Regional Administrator Div. of Reactor Projects:
William F. Kane, Div. Director (Tel: 8-346-5229)
(Region I)
Samuel J. Collins, Deputy Director (Tel: E-3c6-5226)
James T. Wiggins, Branch Chief (Tel: ~E-346-5224)
A. Randy Blough, Section Chief (Tel: E-346-5146)
Lawrence T. Doerflein, Project Engineer (Tel: 8-346-5132)
Senior Resicent Inspector:
Clay C. Warren (Tel: E-617-747-0565)
Resident inspectors:
Jef f rey J. Lyash (Tel: 617-747-0565)
Tae K. Kim (Tel: E-617-747-0565) e
p
)
f
- 11. B.~1
,H1STORICAL PERSPECTIVE'
- SLIDE G 1
i ISSUES
, MILESTONE CHART q
1/80 - 12/87 SALP CYCLE 1 SALP CYCLE 2 SALP CYCLE 3 1/80-12/80 9/80-8/81 9/81-6/82 REPORT ~4/81-REPORT 12/81 REPORT 11/82 i
SALP CYCLE 4 SALP CYCLE 5 12/83-12/84 ORDER TO SALP CYCLE 6 INSP 85-30
~7/82-6/83 7/83-9/84-OUTAGE FOR MODIFY 10/84-10/85 SAFETY SYSTE REPORT 1/84 REPORT 6/85 PIPE LICENSEE REPORT 5/86 FUNCTIONAL REPLACEMENT RADIO-INSPECTION LOGICAL 10/22-11/22/
hh8
'674 HOURS-11/29/84 l
INSP.86-06 PLANT CAL INSP 86-17 DIAGNOSTIC SHUTDOWN 86-10 AUGMENTED SPECIAL SPECIAL INSP~
4/11/86 4/12/86 SAFETY TEAM INSP 2/18-3/7/86 4/12 - 4/25/86 962 HOURS 574 HOURS BECO SHUTDOWN CAL 86-10 MANAGEMENT.
'nASS. REPDF CONTINUATION FOR SUPPLEMENT MEETING 86-41 DN EMERGENC PREPAREDNESS RP"1/24/8612/31/86 12/86 RFO-7 8/27/86 7/86 2.206 PETITION 7/86 I
SALP CYCLE 7 FEfA REVIEW 2.206 LOSS OF OFFSITE INSP 87-53 11/85-1/87 EMERGENCY PETITION POWER (LOOP)
LOOP AUGMENTE REPORT 6/87 PREPAREDNESS 10/87 11/12/87 INSPECTION ISSUES TEAM 8/87 11/16-20/87 380 HOURS 4
S i
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f n
11.B.1
- H1STORICAL' PERSPECTIVE SLIDE 73 p;.
e 1 ^
SALP 'RESULTS PRIOR TO' april 1986 SHUTDOWN ASSESSMENT PERIOD f(C_L_E_1 CYCLE 2 CYCLE 3-CYCLE 4 CYCLE-5 CYCLEJ6 1/80--
9/80-9/81-7/82-
~7/83-10/84--
' FUNCTIONAL' AREAS 12/80 8/81 6/82-6/83 9/84
^ 10/85 OPERATIONS 2
3 3
2-2 3
RADIOLOG1 CAL-CONTROLS 3-2 2-2 3 D-3.' l '
x SURVEILLANCE-2 2-2 1-1 2
MAINTENANCE 2
3.
2
'2 11 2
EMERGENCY PLANNING 3
1 1
1 3D
.3 FIRE PROTECTION
'2 2
3 1-2 SECURITY,
2 2
2 2-2-
2.
ENGINEERING-AND TECHNICAL
' SUPPORT 2
I 11 1-
-LICENSING TRAINING EFFECTIVENESS
~-
-ASSURANCE OF
.0VALITY/0A 3
'3 OUTAGE MANAGEMENT 3
2 2
1 1
l
= _
.e II.B.1.
HISTORICAL PERSPECTIVE-SLIDE ~8 PROGRAM ISSUES LEADING TO APRIL 1986 SHUTDOWN-0 HISTORY OF POOR PERFORMANCE' o
. IMPROVEMENT PROGRAMS INHIBITED BY:
(1). INCOMPLETL DTAFFING, IN PARTICULAR, OPERATORS AND KEY MID-LEVEL SUPERVISORY PERSONNEL, (2)~ A PREVAILING VIEW IN THE' ORGANIZATION THAT THE IMPROVEMENTS MADE TO DATE HAVE CORRECTED THE t
' PROBLEMS, (3) ' RELUCTANCE, BY MANAGEMENT, TO ACKNOWLEDGE SOME PROBLEMS IDENTIFIED BY THE NRC, AND (4) ' DEPENDENCE ON THIRD PARTIES TO IDENTIFY PROBLEMS RATHER THAN IMPLEMENTING AN-EFFECTIVE PROGRAM FOR SELF-IDENTIFICATION OF WEAKNESSES.
REFERENCES:
1.
SPECIAL SAFETY TEAM INSPECTION 50-293/86-06, REPORT 4/2/86 2.
SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE (SALP) 50-293/85-99, REPORT 5/23/86 3.
MANAGEMENT MEETING REPORT 50-293/86-41, P.EPORT 12/31/86 I
O I
-(a E-__._____..__.____.__
j 1,
j
- 1 II B.1
' HISTORICAL PERSPECTIVE SLIDE ~9
).l j
1 TECHNICAL ISSUES LEADING TO april 1986 SHUTDOWN:
r OPERATING
'I 5
10 15' 20 25
-30 DAYS 30 NOV 85 31-DEC 85-JAN 86-28
~*****
28
. FEB 85 MAR 86 11
~*******
6 APR 86 L
REFERENCE:
SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE (SALP) 50-293/86-99, REPORT 6/17/87
- 7 s
' II. B.1 -
HISTORICAL PERSPECTIVE
. SLIDE 10 TECHNICAL ISSUES LEADING TO 1986 SHUTDOUN - (CO"TINUED)
UNPLANNED AUT0w.ATIC SCRAM 5 AND SHUTOOWN5 (11/01/85 - 01/31/87)
P]LGRIM' NUCLEAR ~ POWER STATION Power-Date Level Description Cause 01/03/86 200%
Main turbine generator Equipment f ailure -
bearing vibration random required a controlled plant shutdown for repairs 01/06/86 Restart 4
01/06/86 10%
Reactor scram on ves-Operator error and sel low level during inadequate main-restart. Caused by tenance - excessive operator inattentive-leakage past feed-ness while manually water regulation controlling level-and valves leating feed ater regulation valves (LER 86-003) 02/26/86 200%
With the unit in a Technician error
' half scram configura-and design tion for maintenance deficiency-changeout of a hypersensitive reactor high pressure pressure switches switch, slight bump on the second pressure switch caused a false high reactor pressure scram (LER 86-002) 01/29/86 30D%
A recurrence of main Ecuipment f ailure -
turbine generator random bearing vibration problems resulted in a forced power reduction to 30 percent power
REFERENCE:
SALP REPORT 86-99 f
l L_--_------_--------_---.
l
.L II.B.1 HISTORICAL PERSPECTIVE SLIDE 11 i
TECHNICAL ISSUES LEADING TO 1986 SHUTDOWN (CONTINUED) l Power Date Level' Description Ca'use 03/07/86 200%
Weld leak'in the 4" Equipment-failure head spray piping required a controlled shutdown to, facilitate repairs. (LER 86-005) 03/'2/86 Restart 03/15/86 80%
Increasing unidenti-Ecuipment failure -
fied drywell leakage' random required reactor shutdown. The 11cen-see found and repaired a weld leak on reactor water level instru-enentation line.
(LER 86-006) 03/31/86 Restart
~
04/04/86 100%
A controlled reactor Eauipment shutdown due to the failure -
detection of small oil random leak in the turbine hydraulic control system. (IR 86-07) 04/04/86 E%
During a controlled Equipment f ailure -
reactor shutdown, spurious actuation automatic closure of the MS!Vs of the Main Steam Isolation Valves (M51V) initiated a reactor scram (LER 86-008) 01,/04/86 0%
Following the reactor Operator error scram described above, a second scram signal was received due to the scram discharge volume (SDV) high level-signal (LER86-008) 04/09/86 Restart
[.
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.II.B.1 HISTORICAL-PERSPECTIVE SLIDE 12 TECHNICAL ISSUES LEADING TO 1986 SHUTDOWN (CONTINUED)
Power Date Level Description Cause 04/11/86 93%
Indicated leakage from Equipment failure -
'the reactor water random recirculation system through the 'B' loop Residual Heal Removal-(RHR)' System injection valves forced a shut-down for maintenance 04/11/86 10%
During a controlled Equipment failure -
reactor shutdown,
. spurious actuation automatic closure of the M51Vs of the M51Vs initiated a reactor scram
-(LER 86-DDE/1R 86-07) 04/12/BC C%
A Confirmatory Action Letter 86-10 was issued regarding the April 4 and April 12 MSIV ise-lations and the RHR injection valve leakage.
The Confirmatory Action Letter was subsequently extended to cover correction of signifi-cant programmatic deficiencies. In July 1986, the licensee ceticed te continue the shutdown into 19E7 and conduct refueling, install certain Mark I containment enhance-ments, and complete 10 CFR 50 A;pendix R fire protection modifications, e
Restart of the unit is pending NRC authori-2ation in accordance with Confirmatory Action Letter 86-10.
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11,E.2 HISTORICAL PERSPECTIVE
-SLIDE 13 APRIL 1986 SHUTDOWN CONFIRMATORY ACTION LETTER (CAL) 86-10 i
~
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.o APRIL 11, 1986 PLANT SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS h
WHILE SHUTTING.DOWN AN UNPLANNED SCRAM OCCURRED DUE TO THE o
SPURIOUS PRIMARY CONTAINMENT GROUP 1 ISOLATION, THE OUTBOARD MAIN STEAM ISOLATION VALVES (MSIVs) COULD NOT BE OPENED NRC ISSUED CONFIRMATORY ACTION. LETTER 86-10 ON APRIL 12, 1986 o
AS A RESULT OF THESE RECURRING EVENTS TO MAINTAIN THE PLANT IN A-SHUTDOWN CONDITION UNTIL THE NRC COULD REVIEW IN DETAll THE CAUSES OF THESE EVENTS AND THE LICENSEE'S CORRECTIVE ACTIONS o
CAL 86-10, 4/12/86 REQUIRED:
' MAINTAIN PLANT CONDITIONS TO PROVIDE FOR NRC REVIEW
+
0F THE EVENT
. PROVIDE A WRITTEN REPORT TO THE NRC PRIOR TO RESTART
+
EVALUATING:
A.
INTERSYSTEM LEAKAGE OF RESIDUAL HEAT REMOVAL SYSTEM B.-
SPURIOUS PRIMARY CONTAINMENT ISOLATION SIGNALS C.
FAILURE OF OUTBOARD MSIVs TO REOPEN BECO DECISION 7/86 TO REMAIN SHUTDOWN FOR RFO-7 o
o CAL'86-10, 8/27/86 SUPPLEMENTED TO INCLUDE OTHER HARDWARE AND SALP-RELATED PERFORMANCE ISSUES:
RESOLUTION OF SPECIFIC TECHNICAL ISSUES
+
4 i
/
_y%..
s*'
F
.II.B.2:
, HISTORICAL PERSPECTIVE SLIDE 13-(CONT'Df-FORMAL ASSESSMENT OF THE READINESS FOR RESTART-
+-
0PERATION
-t-FORMAL RESTART PROGRAM AND SCHEDULE ASSESSMENT ~AND RESTART PLAN TO BE SUBMITTED FOR
+-
NRC REVIEW AND: APPROVAL-4 4
1 y
i I I. B.2.
, HISTORICAL PERSPECTIVE SLIDE 14:
~
s,
APRIL 1986 SHUTDOWN CAL 86.
NRC INSPECTION 86-17 o
AUGMENTED SPECIAL SAFETY TEAM INSPECTION o
4/12 - 4/25/86 -IN RESPONSELTO 4/11 PLANT SHUTDOWN o
3-0PERATIONAL PROBLEMS:
(1)
THE SPURIOUS GROUP-0NE PRIMARY CONTAINMENT ISOLATION,-
ON 4/4 AND 4/12/86
-(2)
THE. FAILURE-OF THE MAIN STEAM ISOLATION VALVES (MSIVs).
TO OPEN AFTER THE ISOLATIONS~
(3)
RECURRING PRESSURIZATION EVENTS IN THE RESIDUAL HEAT REMOVAL (RHR) SYSTEM o
BECO APPROACHES TO PROBLEM SOLVING WERE CAREFULLY STRUCTURED AND APPEARED' THOROUGH
}
r ll B.3'
' HISTORICAL ~ PERSPECTIVE SLIDs15 JANAGEMENT MEETING 86-41 o
'. CONDUCTED' 11/24/86'TO DISCUSS ~BECO PLANS FOR. PROGRAM IMPROVEMENTS AT:P1LGRIM AND-THE STATUS OF OUTAGE ACTIVITIES-o TECHNICAL AND PROGRAM ISSUES T0 BE REVIEWED PRIOR T0 STARTUP WERE LISTED AS ATTACHMENT.l TO MEETING REPORT-o
'NRC LOOKING FOR STRONG EVIDENCE OF PROGRESS AT PILGRIM.
PR10rt TO RESTART-o-
NRC-' INTENDS T0 CONDUCT A SYSTEMATIC ASSESSMENT.0F
. LICENSEE PERFORMANCE- (SALP) REVIEW PRIOR TO REACHING A POSITION REGARDING THE RESTART OF THE PILGRIM FACILITY 1-
.y
-p y-11-h
F I I ', B,4 HISTORICAL PERSPECTIVE
' SLIDE 16-
'SALP FINDINGS 86-99
- o ASSESSMENT PERIOD 11/1/85 1/31/87-o SALP. BOARD REPORT. ISSUED 4/8/87.
o SALP MANAGEMENT MEETING'5/7/87
-o SALP REPORT 50-293/86-99 6/17/87 o'
ISSUES:
+
BECO MADE SIGNIFICANT STAFFING AND HARDWARE COMMITMENTS TO IMPROVE PERFORMANCE
+
+.
. PROGRAM IMPROVEMENT BEGINNING TO'HAVE A POSITIVE EFFECT
+-
ASSESSMENT OF PERFORMANCE NOTED SOME IMPROVEMENTS-
'0 ORGANIZATION CHANGES T0: CLARIFY RESPONSIBILITY AND_
~+
ACCOUNTABILITY STABILITY IN STAFFING KEY MANAGEMENT POSITIONS-STAFFING VACANCIES SLOW DEVELOPING IMPROVEMENTS IN SOME PREVIOUSLY IDENTIFIED LONG-TERM PROBLEM AREAS r
o NRC ACTIONS:
o CONTINUE-AUGMENTED INSPECTION PROGRAM o
MONITOR CAL 86-10 ACTIVITIES i
4 a
7.
,1.
II.B 5 HISTORICAL PERSPECTIVE-SLIDE 17 p,<
OTHER ISSUES-f-
o-
. EMERGENCY PREPAREDNESS (1)
ONSITE
- NO SIGNIFICANT DEFICIENCIES OR PROGRAM WEAKNESSES:
(2) 0FFSITE - DEFICIENCIES IDENTIFIED BY COMMONWEALTH REPORT AND FEMA SELF-INITIATED REVIEW
- SIX FEMA DEFICIENCIES. REQUIRE PLAN CHANGES AND SOME-DEMONSTRATION
- ANNUAL FULL PARTICIPATION EXERCISE EXEMPT 10N' GRANTED o
SAFETY ENHANCEMENT PROGRAM (SEP)
(1)
VOLUNTARY PROGRAM NOT A PREREQUISITE FOR PLANT RESTART (2)
BECO IMPLEMENTING SEVERAL SELF-INITIATED ENHANCEMENTS TO THE PILGRIM MARK 1 CONTAINMENT (3)
IMPLEMENTED UNDER 10 CFR 50.59 (4)
NRC HAS REVIEWED SAFETY EVALUATIONS o
LEGAL AND LICENSING ACTIONS (1)
TWO 2.206 PETITIONS HAVE BEEN SUBMITTED REQUESTING THAT BECO SHOW CAUSE WHY PlLGRIM SHOULD NOT-REMAIN SHUTDOWN UNTIL CERTAIN ISSUES HAVE BEEN RESOLVED, PETITIONS REQUEST FULL-ADJUDICATORY HEARINGS TO ADDRESS ISSUES RELATED TO MANAGEMENT, MARK 1 CONTAINMENT AND EMERGENCY PREPAREDNESS (2)
ALL LICENSING ACTIONS HAVE BEEN REVIEWED, THREE REMAINING ACTIONS WILL BE COMPLETED PRIOR TO RESTART i
p.
.i.
- lV. tURC STAFF PRESENTATION SLIDE 1:
- c 1
6 AGENDA
-IV.
NRC STAFF PRESENTAT10fis 4
.A.
ASSESSMENT ACTIVITIES TO DATE L
'1.
RESTART ASSESSMENT PANEL-2.
AUGMENTED INSPECTION AND REVIEW ACTIVITIES 3.
. LICENSING' ACTIVITIES 4.
SALP i5..
INTEGRATED ASSESSMENT' TEAM INSPECTION B.-
FUTURE ACTIVITIES
-C.-
. CONCLUSION g
h.
IV.A ASSESSMENT ACTIVITIES SLIDE 2 MILESTONE CHART PROVIDES FOR TRACKING, PLANNING AND DOCUMENTATION o
OF NRC RESTART ASSESSMENT' ACTIVITIES e
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- lv. A.I' ASSESSi1ENT ACTIVITIES.
SLIDE 4-
~ RESTART' ASSESSMENT = PANEL' o
.SPECIAL RESTART ASSESSf1ENT' PANEL FORi1ED'BY 7/8/87 MEf10RANDUMTONRCREGIONIREGIONAbADMINISTRATOR PANEL CHARTER IS TO COORDINATE THE PLANNING AND' EXECUTION o
OF'NRC. ACTIVITIES AND TO ASSESS-THE RESULTS OF'THESE ACTIVITIES o
RESTART. ASSESSMENT PANEL MEMBERSHIP:
o DEPUTY DIRECTOR, DIVISION OF REACTOR PROJECTS,
-REGION 1.- CHAlRMAN
.O ASSOClATE D1 RECTOR, REGl'ON 1 REACTORS, NRR, CO-CHAIRMAN o
CHIEF, REACTOR' PROJECTS BRANCH 3, DRP o
PROJECT DIRECTOR, NRR o
PROJECTS SECTIONS CHIEF, DRP o
LICENSING PROJECT MANAGER, NRR o
CHIEF, ENGINEERING' BRANCH, DIVISION OF REACTOR SAFETY, REGION 1 CHIEF, RADIOLOGICAL PROTECTION, EMERGENCY PREPAREDNESS o
AND SAFEGUARDS, DIVISION OF RADI ATION SAFETY AIG SAFEGUARDS, REGION 1 PANEL MEETING B1-WEEKLY, EVERY OTHER MEETING AT PILGRIM SITE o
m a.
la IV.A.2l ASSESSMENT'ACTivlT'IESL SLIDE 15 AUGMENTED-INSPECTION AND REVIEW ACTIVITIES 7/8/87' MEMORANDUM FROM' DIRECTOR,;DIVIS10H'0F REACTOR PROJECTS.
o-r T0-THE, REGIONAL ADMINISTRATOR,. REGION I MANAGEMENT OF NRC ACTIVITIES REGARDING-PILGRIM RESTART:
o (1) -UNIQUE PLAN NEEDED FOR MANAGING NRC ACTIVITIES.
NRC'MUST COMP'LETE REVIEWS T0-PROVIDE AN INDEPENDENT (2)
-JUDGEMENT OF PLANTS READINESS FOR OPERATION (3)
MUST PROVIDE FOCUS.AND GUIDANCE TO NRC PROCESS.
o ACTIONS:
-(1)
AUGMENTED INSPECTION PROGRAM T0 IDENTIFY NEEDED IMPROVEMENT AND NEEDED NRC' STAFF ACTIVITIES o
(2)
SPECIAL PILGRIM RESTART ASSESSMENT PANEL - SENIOR STAFF MEMBERS (3)
DIAGNOSTIC TEAM INSPECTION (IATI - INTEGRATED ASSESSMENT TEAM INSPECTION)
(4)
ASSESSMENT REPORT TO REGIONAL ADMINISTRATOR (RAR -
RESTART ASSESSMENT REPORT) k
~
n, i
Y,
.j i..
- 6-
.IV.A.2 ASSESSMENT ACTIVITIES I
. SLIDE 6' AUGMENTED ~ INSPECTION AND REVIEW ACTIVITIES p
INSPECTIONS SALP PERIOD-
_ INSPECTION'OURS ANNUAL HOURS H
i
'1/80-12/80
-1950 1950 9/80-8/81 2328 2328' 9/81-6/82-3735 4482 7/82-6/83 3234 3234 7/83-9/84 4960.
3968 10/84-10/85 3792 3500 11/85-1/87 6762 5409 2/87-5/88 9698 7758' DURING THE.LAST (2/87-5/88) SALP ASSESSMENT PERIOD, NINE NRC TEAM INSPECTIONS-WERE CONDUCTED:
I 1.
APPENDIX-R FIRE PROTECTION PROGRAM REVIEW 2.
PLANT MODIFICATION PROGRAM REVIEW
- 3.
. PLANT EFFLUENT AND ENVIRONMENTAL MONITORING PROGRA 4.
AUGMENTED INSPECTION TEAM'(AITF REVIEW 0F THE LOSS 10F SITE. POWER EVENT ON NOVEMBER 12, 1987 5.
. ANNUAL EMERGENCY PLAN EXERCISE OBSERVATION 4
6.
ONSITE ELECTRICAL DISTRIBUTION ADEQUACY REVIEW 7.
EMERGENCY OPERATING PROCEDURES REVIEW
- 8. -
MAINTENANCE PROGRAM REVIEW-9, IN-PLANT RADIOLOGICAL CONTROLS REVIEW W
_ - - _. - - _. - - - - _... _. _. _ _ _ _ _ - _ - -. - _. _ _.... _. _ _. - - _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. - _.. _ _ _.. _ = -. - - - -_.. _ - _ _ _ - _ _ _ _ - - - - - _ - - _ - _. _ _ _ _ _ _. - - _ - _ _ _ _ _ - _ _ _ -
--_______----__....-_J
i-u-
IV.A.2 ASSESSMENT ACTIVITIES SLIDE 7 AUGMENTED lHSPECTION AND REVIEW ACTIVITIES MEETING ACTIVITIES o
42 MEETINGS CONDUCTED SINCE 4/86 SHUTDOWN o
28 MEETINGS CONDUCTED SINCE 2/87 TABLE 5 0F SALP REPORT 87-99 (SLIDE 8, 9,10) o 8
{
s i
1 1
- _9 ;
y (IV.A.2 LASSESSMENT ACTIVITIES' S_ LID' E 8 -
TABLE 5 MANAGEMENT MEETING AND PLANT TOUR
SUMMARY
'DATE Sp0NSOR' TOPIC..
I
'02/02/87-NRC Management meeting at Plymouth MA to discuss
. the status of licensee improvem,ent prcgrams (IR 87-08) 02/03/87.
Massachustits lecretary of hRC Region I Administrator and other Region'I managers met in Boston, MA with'several Energyf
. Commonwealth administrators'to discuss NRC
- activities regarding Pilgrim 03/09/87-Massachusetts NRC Region'I ' Administrator and other. members of Legislature-
-the staff appeared in Boston, MA before the
' Massachusetts Joint Committee on the Investigation and Study of the Pilgrim Station at Plymouth (IR 87-16) 03/10/87 NRC NRC Chairman Zech toured Pilgrim accompanied by g
the Regional Administrator and attended a licensee presentation (IR 87-16)
~34/27/87
. Massachusetts NRC Region ! Administrator and other members of Legislature the staff appeared in Boston before the Mass-chusetts' Joint Committee on the Investigation and Study of the Pilgrim Station _in Plymouth (IR 87-38) 15/01/87 NRC Management meeting at NRh Region I to discuss a surveillance program violation and program weannesses (IR 87-23) 5/07/87 NRC 1987 5 Alp management meeting at Plymouth, MA 5/32/87 NRC NRC Commissioner Carr toured the plant and attended a licensee presentation i/27/87 Plymouth Board of Four NRC Region I management representatives participated in a public meeting in Selectmen Plymouth, MA
./24/87 NRC NRC Commissioner Asseistine toured the plant and attended a licensee presentation
~~
\\
IV.A.2-ASSESSMENT ACT2VITIES t
I Table 5.
SLIDE 10 3
f DATE' SPONSOR TOPIC 01/07/88 United Regulation and.the Region I Admin States Senator or appeared before the Senate Labor and Human Kennedy Resources Committee regarding Pilgrim public hearing was held in Plymouth, Ma The 02/28/88 NRC NRC Region I and NRR managers conducted a meeting in Plymouth, MA to solicit public public comments on the licensee's Restart Plan 02/24/88 NRC Management meeting at NRC Region } to di the licensee's self assessment process t scuss used for determining restart readiness (IR o be 88-10) 03/10/88 NRC Region I Administrator toured the pl e
interviewed licensee staff regarding the d basis for the direct torus vent modification esign' 85-07) n (IR 04/08/88
'NRC fanagement meeting at NRC Region I to discuss the licensee's proposed power ascension t program (Meeting Minutes 88-43) est 04/22/88 NRC NRC Commissioner Carr toured the plant and g
attended a licensee presentation (IR 85-12) 05/06/88 NRC NRC Commissioner Rogers toured the plant attended a licensee presentation (IR 88-19) and 05/31/88 NRC HRC Region I and NRR managers conducted a meeting in Plymouth, PA to provide public responses to comments and concerns on the licensee's Restart Plan raised during the 2/38/88 public meeting (Meeting transcript)
7-
-l l
9.
- lV.A.3.
. ASSESSMENT ACTIVITIESi SLIDE ~12:
o i
LICENSING ACTIVITIES
~
i OL RESOLUTION OF 2.206 PETITIONS.
I o.
.-SAFETY ENHANCEMENT' PROGRAM'(SEP) REVIEWS
'l TECHNICAL SPECIFICATION. LICENSING. ACTIONS - 3.lTEMS 0-REMAIN OUTSTANDING FOR RESTART:
- (1)- FIRE-PROTECTION APPENDIX A FIRE WALL l RATING' CLARIFICATION (2)
DEGRADED GRID VOLTAGE'-
(3)
ORGANIZATION CHANGE l,
l-l
_~.w
.____...__-w.m__
-_.s
____.__-2_..u_<m.-___
-_.-_-__a____mm_
-__m
___--a.___--
-m_-m-m-m__.a_______m__-____--.-____._t__
x._
_a
l
-a IV.A.i ASSESSMENT ACTIVITIES SLIDE'13
~
SALP REPORT Pilgrim SALP History Assessmant Period-Post Shutdown l
1/80-9/80 - 9/81-7/82-7/83--
10/84-11/85-' 2/87 Functional Area 12/80 8/81 6/82 6/83 9/84 10/85 1/87 5/88.
Operations 2-3 3
2 2
3 2
2 Radiological Controls' 3
2 2
2 30 31 3
32 Surveillance 2
2 2
1 1
2 3
2 Maintenance 2
3 2
2 11 2
2 2
Emergency Planning 3
1 1
1 3D 3
2 21 Fire Protection 2
-2 "
3 l'
2 3
2 Security 2-2 2
2 2
2' 3I 2
Engineering and Technical Support 1
1 Licensing 2
1 11-1 2.
2 Training Effectiveness 2L 2
Assurance of Quality /0A 3
3 3
2 Outage Management 3 2
2 1
1 1
IV.A.4-ASSESSMENT ACTIVITIES SLIDE 14 SALP 87-99.
o ASSESSMENT PERIOD:
2/1/87-5/15/88 o.
SALP BOARD:
7/5-6/88 o
BOARD REPORT ISSUED:
7/27/88 o
MANAGEMENT' MEETING:
8/25/88 o
ISSUES.
PERSONNEL AND ORGANIZATIONAL CHANGES CONTINUED THROUG
+
THE PERIOD, FUNCTIONAL REPORT CHAINS WORKING WELL SIGNIFICANTLY HIGHER STAFFING ALLOCATIONS
+
AGGRESSIVE ACTIONS IN MOST PROGRAM AREAS OF WEAKNESS
+
-SOME DELAY IN It1PLEMENTAT10N OF IMPROVEMENTS o
CONCLUSIONS:
-(1)
EXTENSIVE BECO EFFORTS TO IMPROVE CORPORATE AND SITE MANAGEMENT ORGANIZATION STRUCTURE
' (2)-
EFFORTS GENERALLY SUCCESSFUL IN CORRECTING STAFFING, ORGANIZATION AND MATERIAL DEFICIENCIES (3)
SELF-ASSESSMENT PROCESS SUCCESSFUL IN TARGETING P,ANAGEMENT ATTENTION (4)
PERFORMANCE lh SOME AREAS LAGS BEHIND DUE TO LATER IMPLEMENTATION OF PROGRAM AND ORGANIZATIONAL IMPROVEMEN DUE TO HIGHER PRIORITY OUTAGE WORK (5)
A CONTINUED BECO COMMITMENT IS NEEDED TO SUSTAIN THE OVERALL IMPROVING TREND IN PERFORMANCE
_ _ _ _ _ _ _. _ ~ _ _. - - - - - - ~ - - - - - ' - ' ^ - " - ^ ~ ~ - -
gp e.
I I
1 t
c IV.A.5
_ ASSESSMENT-ACTIVITIES St IDE 15 INTEGRATED ASSESSMENT' TEAM INSPECTION x
- (lATI)
.(
COMMITTED TO " CONDUCT A REGION I DIAGNOSTIC TEAM o
AFTER DECO SUBMITTED 1TS: READINESS INSPECTION RE L
THE PILGRIM RESTART ASSESSMENT PANEL HAS INDEPEN A.
THAT LICENSEE PROGRAM AREAS ARE REASONABLY. READY T
,F THIS' INSPECT 10N."(1) 6/25/88 BECO LETTER 88--099' REQUESTED THE NRC TO COM
.o INTEGRATED-ASSESSMENT TEAM INSPECTION (IATI) ON 7/11/8 ON COMPLETION OF THE BECO RESTART READINESS SELF-ASSE (RRSA) AND IDENTIFICATION AND SCHEDULING OF REMAININ TO BE DONE BEFORE RESTART.
7/11/88 NRC LETTER CONFIRMED REVIEW 0F RRSA AND SCHED
'o IAT1.
REFERENCES:
(1):; MANAGEMENT 0F NRC ACTIVITIES REGARDING PILGRIM RESTART, MEMORANDUM 7/8/87 l
1
- p.,.i iw _ _ _- _.
D.
.IV.A,5
. ASSESSMENT ACTIVITIES' SLIDE 16-IATI~iCONTINUED) o IATI PURPOSE:
t 1.
"TO INDEPENDENTLY REVIEW:AND ASSESS THE' READINESS OF.YOUR MANAGEMENT CONTROLS,. PROGRAMS AND PERSONNEL.-
TO SUPPORT SAFE RESTART.0F.THE FACILITY."II)
.o IATI' SCHEDULE" ONSITE PREPARATION 7/19-21/88 lNSPECTION 8/8-19/88 DOCUMENTATION 8/20-24/88'
. INSPECTION EXIT MEETING 8/24/88 0
IATI OPERATING. PLAN OBJECTIVE:
"THE NRC HAS PERFORMED NUMEROUS INSPECTIONS TO'.
DETERMINE THE. STATUS AND ADEQUACY OF THE IMPROVEMENTS.
THE OBJECTIVE OF THE lATI.ls T0 REVIEW THE ADEQUACY OF ANY= ISSUES NOT PREVIOUSLY. INSPECTED OR WHICH
. j REQUIRED FOLLOWUP INSPECTION, TO DETERMINE IF
. 1 IMPROVEMENTS MADE ARE EFFECTlVE AND APPEAR LONG.
LASTING, AND TO DETERMINE IF BECO IS PREPARED T0 SUPPORT THE RESTART AND SAFE OPERATION OF PILGRIM."-
REFERENCES:
(1) - NRC LETTER TO BECO, 7/11/86
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,'yy,A.5-ASSESSMENT ACTIVITIES'
' SLIDE 17 E
.IATI (CONTINUED)
~ ATTACHMENT.A f
ORGANIZATION LJ SENIOR.
l-l. MANAGER l
4
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l S.. Collins ~l l-l 1
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I l-TEAM l
l TECH I
I LEADER.
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ASST.
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R. Blough j'
~l C. Warren l l'
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1 M.J. Di0onato I I
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l SHIFT INSPECTORS l l
l SPECIALIST INSPS l-
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-l l L. Rossbach l
l T. Dragoun j
l B. Raymonc:
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G. Smith l
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L'. Plisco l
l D. Mcdonald l
l F. Akstulewic:
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J. Lyash I
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l L. Doerflein l
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l M. Evans i
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- IV. A. 5'-
ASSESSMENT ACTIVITIES-SLIDE l'8-
_IATI (CONTINUED ) -
ATTACHMENT B Pilgrim lATI Roster Senior Manager:
Sam Collins Team Leader:
_ Technical Assistant:
Randy Blo'gh u
Administrative Assistant:
Clay Warren Mary Jo DiOonato -
Shift Inspectors:
Larry Rossbach Loren P11sco-Bill Raymond Frank Akstulewicz Specialist inspectors:
HP:
Tom Dragoun Security:
Greg Smith Maintenance:
Jeff Lyash (Bill Raymond)
Surveillance:
Larry Doerflein (Frank Akstulewicz)
Training / Management:
Dan Mcdonald Michele Evans
' Additional Area Assignments:
Fire Protection:
Larry Rossback OA/DC:
Review Committees:
Loren Plisco Loren Plisco (Frank Akstulewicz)
Inspection Report Coordinator:
T. J. Kim l
i L
h._____---.__m____-_._-__m.--_-__m
__________-.__.______m
i 1
IV.A.5 ASSESSMENT ACTIVITIES' 1
SLIDE 19 1
a lATI CONCLUSIONS o
EXIT MEETING CONDUCTED
.8/24/88 o
-IATI REPORT SCHEDULE 9/2/88 o
PUBLIC MEETING SCHEDULE WEEK.0F 9/9/88 e
(
>e oS IV.B FUTURE ACTIVITIES SLIDE 20L FUTURE ACTIVITIES lATI
MGT SUBCOMMITTEE REPORT MEETING
-MEETING I
I l
8/24/88 8/25/88 8/26/88 9/2/88-
.s ACRS RESOLUTION E0P 2.20G RESTART / CAL FULL OF SEP-ISSUES COM MTG ISSUES ADDRESSED-ISSUE ISSUE-1 STATUS STATUS I
i i
i 9/7/B8
)
POWER 1ATI
'2.206 NRC ASCENSION PUBLIC PUBL]C RESTART PROGRAM MEETING REVIEW MEETING ASSESSMENT-REPORT I
I I
I W/0 9/19/88-W/0 9/19/88 9/30/88 s
RESTART ASSESSMENT PANEL EMERGENCY RECOMMENDATION TO. REGIONAL PREPAREDNESS REGIONAL ADMINISTRATOR ISSUE ADMINISTRATOR STATUS
.RECOMMENDAT10N TO DIRECTOR, NRR I
D/NRR COMMISSION COMMISSION RESTART RECOMMENDATION ERIEFING ASSENT DECISION
I COMMISSION CORRECTIVE DISSENT ACTIONS u
POWER NRC NRC I
I ASCENS10h RELEASE ASSESSMENT /SALP
)
PROGRAM 1
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IV.C
. CONCLUSION-
-SLIDE 21 f
CONCLUSION o
PILGRIM SHUTDOWN APRIL 12, 1986 DUE TO TECHNICAL ISSUES (MSIVS, CONTAINMENT ISOLATION AND INTERSYSTEM LEAKAGE T0 RHR SYSTEMT SHUTDOWN CONFIRMED BY CAL 86-10 0F 4/12/86 o
ISSUES AND NRC CONCERNS EXPANDED BY SUPPLEMENT TO o
CAL 86-10, 8/27/86, WHICH REQUIRED A FORMAL ASSESSMENT BY BECO OF THEIR READINESS FOR RESTART AND A FORMA RESTART PROGRAM WITH A SCHEDULE BE SUBMITTED TO TH NRC BECO HAS DEVOTED SUBSTANTIAL RESOURCES TOWARDS TNE o
RESOLUTION OF THE ISSUES AND THE NRC HAS REVIEWLa ACTIONS REGARDING MANAGEMENT AND ORGANIZATIONAL CHANGES, NEW PROGRAMS AND IN-PLANT IMPROVEMENTS THE LEVEL OF NRC STAFF ACTIVITY ON PILGRIM IS VERY o
HIGH AND WILL REMAIN HIGH IN CONJUNCTION WITH RESTART ASSESSMENT ACTIVITIES-j THE LEVEL OF COMMISSION INTEREST AS WELL AS PUBLIC o
INTEREST IN THE FACILITY IS HIGH
f, IV.C-CONCLUSION-
_ SLIDE 22-i CONCLUSION (CONTINUED)
RESTART CRITERIA STABLE AND EFFECTIVE MANAGEMENT AND STAFF AT PILGRIM RESOLUTION OF MAJOR TECHNICAL lSSUES DEMONSTRATED IMPROVEMENT IN SALP PROBLEM AREAS MAINTENANCE PROGRAM AND WORK BACKLOG ISSUES ADDRESSED NRC SATISFIED THAT CERTAIN EMERGENCY PLAN IMPROVEMENTS HAVE BEEN MADE s
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I UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS TECHNICAL MEETING - AUGUST 26, 1988 REVIEW OF PILGRIM NUCLEAR POWER STATION RESTART ACTIVITIES MEMORIAL HALL 83 COURT STREET PLYMOUTH, MASSACHUSETTS
, MEETING HANDOUT 1.
PRESS RELEASE 2.
AGENDA r
3.
SUBCOMMITTEE BACKGROUND l
1
e.
ENCLOSURE 1 UNITED ST'ATES
/""%'i NUCLEAR REGULATORY COMMISSION
'/
OFFICE OF GOVERNMENTAL AND PUBLIC AFFAIRS, REGION I
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475 Allendste Road, King of Pruuta. Ps.19406 Tel. 215 337 5330
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No. 1-88-134 August 16,1988 Centact: Karl Abraham NRC 5AFETY ADVISORY GROUP TO MEET AUGUST 25 AT PILGRIM NUCLEAR PLANT IN FLYM3UTH, M455ACNUSE775 A subcommittee of the Nuclear Regulatory Comission's Advisory Comittee on Reactor Safeguards (ACRS) will hold a technical meeting on August 26 in Plymouth, MA, to discuss the preposed restart of the Pilgrim nuclear power plant in Massachusetts.
The meeting, which is open to the public, will begin at 8 a.m. at the Memorisi Hall, 63 Court Street. Representatives of the NRC staff and of the Boston Edison Company, which is licensed by NRC to operate Pilgrim, will participate in the meeting.
The ACR5 is a statutory Comittee establis'hed to advise the Coeraission on the safety aspects of proposed and existing nuclear facilities and the adequacy of proposed reactor safety standards, and to perfom such other duties as the Ce utssion may request.
In the past, the ACR5 has looked at several selected plants that were shut down because of operating or sanagement problems.
The Pilgrim plant has been shut down since April 1986, because of equipment and management issues, and to conduct a refueling and maintenance outage.
Additional information on the meeting may be obtained from Mr. Paul Boehnert, ACRS, (202) 634-3257.
I t
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8/22/88 o
ENCLOSURE 2 Advisory Conunittee on Reactor Safeguards Meeting of the Ad Hoc Subcommittee on Pilgrim Restart Plymouth Town Hall August 26, 1988
- Top.ical Agenda -
l-Actual l
Time I. Introduction - W. Kerr, Subcorxnittee Chairman 8:00 a.m.-
II. NRC Staff Presentations - S. Collins A.
Introduction B.
Historical Perspective-Issues 1.
Issues Leading to April 1986 Shutdown 2.
April 1986 Shutdown, Confirmatory Action Letter (CAL) (86-10) 3.
November 1986 mnagement Meeting (86-41) 4.
SALP Findings (86-99) 5.
Other Issues III. Boston Edison Company (BECo) Presentations 9: 30 a.m.
A.
Introduction - R. Bird B.
Response to Issues, Restart Programs, Plans and Status - R. Bird /K. Highfill 1.
Senior Nuclear Management 2.
Plant Status 3.
Major Projects 4.
SALP Report 5.
INPO Review
Rev. 1 8/22/88 Pilgrim Topical Agenda 2
August 26, 1988 Actual Time C.
Major Prograns - C. Highfill 1.
Contractor Ranpdown t-2.
Overtime Controls 3.
BECo Staffing (address-staffing of SRO's/RO's) 4.
Quality Performance D.
Major Plant Areas - K. Highfill/R. Anderson 1.
Total Maintenance Requests (MRs) 2.
Power Block MRs 3.
Radiation Protection 4.
ALARA 5.
Operational Readiness E.
Safety Enhancement Program - J. Howard/D. Blanchard/
R. Henry 1.
Goals 2.
Analysis 3.
Program Elements 4.
Approach 5.
Results 6.
Direct Torus Vent System 7.
Summary F.
Other Issues - R. Varley 1.
Emergency Planning 2.
Problems (if anyl Regarding Lighting Strikes
kh{
kev. 1 8/22/88 vp l Pilgrim Topical Agenda 3
August 26,1988 R'
1 2-Actual Time
- LUN01 ***
12:00 p.m..
IV. NRC' Staff Presentations - S. Collins 1:00,p.m.
A.
Assessment Activities to Date 1.
Restart Assessment Panel
- 2. -. Augmented Inspection and Review.
Activities 3.
Licensing. Activities 4.
SALP 5.
Integrated Assessment Team Inspection
.B.
Future Activities C..
Conclusion 2:30 p.m.
V. Public Comment Period 2:35 p.m.
"
- BREAK **
- 4:30 p.m.
VI. Subcm nittee Discussion 4:45 p.m.
VII. Adjourn 5:00 p.m.
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I ADVISORY COMMITTEE ON RE ACTOR sAFEGUARos ENCLOSURE 3 j -Q 'p wasect oA. D c. 20e45 j
July 1, 1988 WILLIAM KERR Dr. William Kerr was born in Sawyer, Kansas, on August 19, 1919. He-received' his Ph.D. in electrical engineering from the University cf Michigan in 1654 ar.d was awarded his B.S. and M.S. (EE) f rom the University of Tennessee ir 1942 and 1947, respectively.
Dr. Kerr joined the University of Michigan faculty.in 1953, becoming Professor of huclear Engineering in 1958. He was Project Supervisor, AlD (ICA) Nuclear Energy Project from 1956 until 1965.
From 1961-74 he was Chairman of the Department of Nuclear Engineering and currently is Professor of Nuclear Engineering -and Director of the Ofiice of Energy Research at the University. Prior to joining the University of Michigar f aculty, he was an instructor and assistant prof essor at the University of Tennessee.
Dr. Kerr's professional career has also included assignments as a consultant to Atomic Power Development Association, the Oak Ridge National Laboratory anc.the Unitec States Department of State in areas related to the development and application of nuclear energy.
1 He is the author of publications on atomic energy, its application to devices such as a beta ray microscope, on nuclear engineering educa-I tier, and on reactor safety.
r llow of the American Nuclear Society, and of the AAAS, Dr. Kerr is a e
Senior Memoer of the IEEE, and a member of the American Society of Engineering Educetion, he received the A. H. Compton Award of the American Nuclear Society in 1964 He is a member of several honorary i
societies including Sigma Xi anc' lau Beta Pt.
]
I Dr. Kerr was appointed to the statutory Advisory Comittee on Reactor
)
Safeguards in 1972 and was elected Chairman of the Comittee for calendar years 1975, 1987, and 198B.
He was reappointed to the Comittee in 1976, 1980, and 1984.
Dr. Kerr is married to the fomer Ruth Duncan. They have three sons, William, Joht and Scott. They reside in Ann Arbor, Michigan.
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July 1, 1988 l
E JAMES C. CARROLL Mr. James Carroll was born in San Francisco, California, on June 27, 1930.
He attended the University of California at Berkeley and in 1952 received his B.S.
in chemical engineering.-
Mr. Carroll began his career with Pacific Gas and Electric (PG&E) in 1952, retiring in October 1987 as Manager, Nuclear Operations Support Department.
During his career, Mr. Carroll was associated with the operation of PG6E's
~ fossil fuel, geothemal, and nuclear power-plants.
He has been involved with ell of PG6E's nuclear power plants, beginning in 1957, when he was the senior PG&E technical person on-site at the Vallecitos Atomic Power Plant, the first privately owned nuclear power plant to receive an AEC operating license. While there, he became the first U.S. Utility company employee to receive a Reactor Operator License.
He later served on loan as a shift nuclear er,gineer responsible for-support of operations and conduct of the startup test program at Dresden huclear Power Station, the first full-scale commercial nuclear power plant in the nation.
He subsequently served in inanagement positions associated with the Humboldt Bay Nuclear Unit, where he received an AEC Senior Reactor Operator License, and the Diablo Canyon Power Plant.
During his career, Mr. Carroll also held several managerial positions responsible for operations, maintenance, personnel training, infomation management, and plant staff support functions, He served on PG&E's Ger.arai Office nuclear piar.t safety review comittee and its special task force convened to study and evaluate the Three Mile Island accident.
Mr. Carroll is a Registered Pccfessional Engineer-Nuclear Engineering in j
the state c' Celifornia and a member of the Anerican Nuclear Society.
He has had long involvement in nuclear standards activities.
He is also a charter memoer and past chairman of.the Edison Electric Institute, Nuclear Power Subcommittee.
Mr. Carroll was appointed to the statutory Advisory Comittee on Reactor Safeguards in June 1985.
Mr. Carroll is merried to the former Jacqueline Hviler.
They have two sons, Andrew and Peter. He and his wife reside in Orinda, California.
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July 1, 1988 CHARLES J. WYLIE Mr. Wylie was born in Morganton, North Carolina, on June 20, 1926.
He graduated from the University of South Caroline in 1950 with a Bachelor of Science degree in electrical engineering. He began his professional career with Duke Power Company in-1950 and retired as Chief Engineer of the Electrical Division, Design Engineering in September 1984 His involvement with nuclear power begen in 1956 when' he participated in the engineering and casign of the first nuclear power electric generating station in the Southeastern United States, the pressurized heavy water. tube reactor plant (CVTR-PWR) at Parr Shoals. South Carolina.
From 1965 until he retired in 1984, he had total electrica1' engineering and design respon-sibility for all of Duke Power. Company's' new generating f acilities which includes the Oconee, McGuire, Catawba and Cherokee nuclear stations, the coal-fired Marshall and Belews Creek Stations, and the Keowee, Jocessee, and Bad Creek hydro stations.
Mr. Wylie was the Unitec States' representative to the working group which prepared the International Atomic Energy Agency ' Safety Guide on Safety-Related Electrical Power Systems for Nuclear Power Plants SG-D7" and related " Assessment Guide."
Mr. Wylie is a Fellow of the Institute of Electrical and Electronics Engineers (IEEE) having long involvement in nuclear standards activities, chairing ~ numerous comrittees, and is a present member of the Standares-Board.
He recently receivec the IEEE Centennial Medei for Extraordinary Achievement in Electrical Engineering.
He is a member of the American huclear Society anc hes also been a comittee member of the Edison Electric Institute's and the Electric Power Research Institute's Electrical Systems and Equipment Comittees and past chairman of the American Society of Mechanical Engineers' Werking Group on Reactor Coolant Pump Motor Frames.
He was appointed to the stetutory Advisory Comittee on Reactor Safeguards on September 5,1964.
Mr. Wylie resides with his wife, Margaret Jo, in Charlotte, North Carolina.
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