ML20236F020
| ML20236F020 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 10/26/1987 |
| From: | Bird R BOSTON EDISON CO. |
| To: | |
| Shared Package | |
| ML20236F025 | List: |
| References | |
| PROC-871026, NUDOCS 8710300106 | |
| Download: ML20236F020 (240) | |
Text
.
Pilgrim Nuclear Power Station l APPENDICES TO t
l RESTART PLAN VOLUME 2
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Pilgrim Nuclear Power Station APPENDICES TO 9
RESTART PLAN o
l VOLUME 2 REV.1 ;
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'l' LIST OF APPENDICES l
l 1
- 1. Restart Plan Flow Chart .J
- 2. . Level I RFO-7 Schedule
- 3. Licensed Reactor Operator Complement Projection. l-j R
- 4. Staffing Levels in Key Areas I 1
- 5. Performance Excellence Indicators ,
i
- 6. Summary Status-of RestartJActions in MCIAP
- 7. Summary Status of Restart Actions in RAP
'8. Status of CAL No. 86-10 Items.
- 9. Status of Management Meeting 86-41 Items
- 10. ,
Restart Regulatory Responses
- 11. Proposed Changes to Regulatory Commitments
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- 12. Systems Group Review Summary Reports i I
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BEco BECo BEco, : Contractors Positions complement-Complement Employees Jin'BECo Unmanned' Positions-
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- ; .Ai?PENDIX 6 EXECUTIVE
SUMMARY
-A numerical ~ sum' nary . of the status .of Material- Condition 1
-l Improvement. Action Plan items follows: ,
'k o Total ~ items in Appendix 6:............. 89 '
(All!are designated RESTART)
~
1 o' Total' items " COMPLETED":...............
10 'I i
o Tc tal items ~ " CLOSED" : '. '. '. . . . . . . . . . . . . . . . 67 -
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'XPPENDIX 6 N l'u ,
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SUMMARY
STATUS 07) RESTART ACTJONS IN MCIAP
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}
This appendix. summarizes the status of' those items- in the ag
,A d Material Condition Improvement Action ' Plan that are required to ,
be ' completed prior to or in conjunction with startup. . ->
No,tations in the "DUE/ STATUS" are used as follows: '
- r. j (DATE) Means that work on the item is, ,
I finished and the date 3 not J' indicates when the . action; is expected to ;be complete eand ' y/ /' ]
ready for senior management ,
review.
RESTART Means that the action is '
directly tied to or part of the actual reactor startup evolution or power ascension ,
j l t
program. !f
- COMPLETED Means that the cognizant manager considers the O results achieved satisfy ;
l d: the action requirements, but that senior management' is conducting
- a. review before approving final closure of the l.
, t item.
- + CLOSED Means' that senior management review has f I
been completed, the j
actions have received' fint.1 approval 'and .the, r.j documentation has been-retained in an item ;
closure flie. i l
The numbering system for action items contained in this appendix {
uses'as the first two digits "03", (0?-XXX-XX) which indicates l the action is related to some maintenance' function. Appendices 'l
]
8, 9 and 10 also contain maintenance relsted items and also use the "03" prefix, but in those appendices the actions are limited
]
to those which involve a regulatory commitment. To differentiate j between the two groups of maintenance items (non-regulatory and i regulatory), the second set of digits in' the action number of a p regulatory maintenance item ' begins s with . "9" (i.e. 03-9XX-XX). j l Maintenance items in Appendix 6 use "0" as the first of the !
V second set of digits, (i.e. 03-0XX-XX).
j
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( 0 Date:. October 22, 1987 7%.
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I (7
f
SUMMARY
STATUS OF RESTART ACTION IN.'
' ," MCIAP o e a '
/
,.{
ISSUE /AC,Tlp,H DES,Q.RIPTION DUE/ STA'EUS_
- -t
' t} , ftRGANIZATION AND STAFFING' 03-O'01
>y a' i. Y COMPLETED
'03-001-01-TH: PROMULGATE ORGANIZATION
\' .
,n... ;
CLOSED
.G3-001-02-TR BRIEF MANAGERS &: SUPERVISORS l i ____-____-___._:-__..-____-_________.l-__-_-..___--___________--___--_-
'03-004 ADMINISTRATIVE DEMANDS.
ASSIGN CONTRACTOR AUTHORITY .. ' CLOSED-03-004-01-MA CLOSED t 03-00602-MA . IDENTIFY INAPPROPRIATE ACTIVITIES n' ,: >
, ' CLOSED
.03-004-03-MA REDUCE SUPERVISOR ACTIVITIES 005 WORK PERFORMANCE STANDARDS COMPLETED 03-00b-01-TR PREPARE BRIEFING MATERIALS Dg' j.,
COMPLETED
- 03-005-02-TR,jBRIEF SUPERVISORS ,.
CLOSED.
03-005-03-MA- MANAGER WORKSITE TOURS SR MANAGER WORKSITE TOURS
' CLOSED 'i 03 -005 MA
' COMPLETED 03--055-05 aCL e CONTRACTOR WORKSITE TOURS,.
- p-CLOSED 03-005-06-TR INPO OBSERVATION TRAINING COMPLETED 005-07-MC ASSIGN MAINTENANCE COACH.
PREPARE VISUAL DISPLAY CLOSED. ;
03-005-08-MC t
CLOSED 03-005-12-MA REVISIT CLOSED ITEMS
-____---_..__-------__--_-_-_---__---__-_____-__----_---_-_-_----_---__ .i I
03-007 PROCEDURE VALIDATION i CLOSED 03-007-01-PS IMPLEMENT PROCEDURE COVER SHEET CLOSED l 03-007-02 PS PROCEDURE VALIDATION RESP
.V O '
APPENDIX 6
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'v~ Date:.dctober'22,-1987 1
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SUMMARY
- STATUS OF RES1?RT ACTION . IN !
MCIAP j Y-dY -
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M
-l% DESCRIPTION,7 'f 7 / Mi
.. ./ ISSUE / ACTION ,.
, /: _ qs ~ ' q q/. 1 7: '.
y
- d 03-008. MATERIAL' CONDITION
- & BOUTEKEEPING-
-008-01-MC ' DECONTAMINATE'ON[ SCHEDULE 30 OCT 87 30~OCT 87,
+V ,y~. 03-008-02-MC DECON PRIORITY AREh9 u
( A_
' 03-008- O?yNC LEAK REPAIR AND DECON POLICY CLOSED: l
]f CL:) SED
' 03-0 0 8 -0 4 -MA .DECON PROGRESS-INDICATOR r
.lf
<03-009 PERFORMANCE GOALS O. 03-009-01-HR .BRIEF ALL MANDS ON GOALS CLOSED. l w
CLOSED t,) 03-009-02-H} ' GOALS ACHIEVEMENT CRITERIA.
.-----------q----------------------------------------------------------.
'03-010 f. COMMUNICATIONS I
303-010-01-ith -ISSUE ACTION PLANS -
CLOSED' ;
.s
} +
A j '
CLOSED !
- '4,03-010 02-KA SHORTCHANGE MR SCHEDULE- J & #
8 I
/-, -
. h (
CLOSED
.j03'-_030 03-M.L RESTART-PROGRESS ASSESSMEKf' ,},*
it
" is 03-010-04-MA' PERFORMANCE EXCELLENCE TEAM # CLOSED R -4 f i! _
7 .
COMPLETED
" 03-010-05-MA' TRITT , COORDINATORS ^
.)Y DAILY REVIEW OF MRS CLOSED 03-010-06-MA y l 03-012 MANAGEMENT FEEDBACK 03-012-01-MA PUBLISH OUTAGE SCHEDULE CLOSED f
, 03-012-02-OM USE THREE-WEEK SCHEDULE CLOSED s- - -!
If I - .
CLOSED d' 03-012-03-OM WORK PROGRESSING GROUP
'", , + _
03-012-04-OM PROGRESS CLOSED .
EEDBACK f a--------------------------------------
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r f'>'
' ' ' AIPENDIX 6
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Date: October 22, lo87
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SUMMARY
STATUS OF RESTART ACTION IN j MCIAP-
' ISSUE / ACTION DESCRIPTION DUE/ STATUS
~03-013 MAINTENANCE REQUESTS j
03-013-01-MA ASSIGN MR REVIEW TEAM CLOSED D'
03-013-02-PL REVISE MR PROCEDURE- CLOSED. !
03-013-03-TR MR PROCESS TRAINING CLOSED
______________________________________________________________________ q 03-015 MAINTENANCE PROCEDURE CONTROL 03-015-01-PS MAINTENANCE PROCEDURE ISSUE CLOSED l f
03-015-02-PS SRO PROCEDURE CHANGES 30 OCT 87 l n;03-016 MAINTENANCE PLANNING Yn .
CLOSED 7' N 03-016-01-PL RFO-7 APPROVED TASK LIST !
k_') .
CLOSED 1
I
. 03-016-02-PL RFO-7 WORK SCOPE REVIEW COMMITTEE i
3 03-016-03-PL RFO-7 WORK SCOPE CHANGES CLOSED l 1
03-016-04-PL RFO-7 MASTER SCHEDULE CLOSED ]
I 03-017 POST-MAINTENANCE TESTING 03-017-01-TE REVIEW TESTING PROGRAM CLOSED n
03-017-02-TE PREPARE TESTING SCHEDULE COMPLETED {
03-017-03-PS REVISE TESTING PROCEDURE 30-OCT-87 1
03-017-04-TE ESTABLISH " TIGER TEAM" CLOSED j i
03-017-05-TE IDENTIFY TESTING REQUIREMENTS 30-OCT-87 )
- IrV,.
______________'__________________________________________ 1 03-019 CENTRALIZE PLANNING FUNCTIONS 03-019-01-OR ESTABLISH PLANNING AND RESTART GRP CLOSED !
I f
l APPENDIX 6 s
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t-Date:. October 22, 1987-
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SUMMARY
STATUS.OF RESTART ACTION IN MCIAP t
-ISSUE / ACTION DESCRIPTION DUE/STAIME 03-019-02-PL RFO-7' APPROVED TASK LIST CLOSED' 03-019-03-PL. RESOLVE RELOAD ITEMS COMPLETED. ;
03-019-04-PL -PLAN RFO-7 WORK ITEMS CLOSED 03-019-05-PU- ' ASSIGN MATERIAL EXPEDITORS. CLOSED 03-019-06-PL AUGMENT MAINTENANCE PLANNERS CLOSED-019-07-PL PACKAGE WORK ITEMS CLOSED 03-019-15-PL RESOLVE RESTART ITEMS 26-OCT-87' 03-019-16-PL RESOLVE ~ RESTART ITEMS (QA) CLOSED CLOSED 03-019-17-PL RESOLVE RESTART ITEMS (NSRAC) 03-019-18-PL RESOLVE RESTART ITEMS (RA&P) - 30-OCT-87
-{
03-019-19-PL RESOLVE RESTART ITEMS (INPO&SALP) 30-OCT-87 CLOSED 03-019-20-PL RESOLVE RESTART ITEMS (ORC)
CLOSED 03-019-21-PL RESOLVE RESTART ITEMS-(EP) 03-019-22-PL RESOLVE RESTART ITEMS . (MAT'L) 30-OCT-87 RESOLVE RESTART ITEMS (TEMP MODS) CLOSED 03-019-23-PL 03-019-24-PL RESOLNE RESTART ITEMS (PIP'S) CLOSED CLOSED 03-019-25-PL RESOLVE RESTART ITEMS (HP) 03-019-26-PL- RESOLVE RESTART ITEMS (LER) CLOSED l CLOSED !
03-019-27-PL RESOLVE RESTART ITEMS (SPI)03-020 WORK ASSIGNMENT PRACTICES 4
03-020-01-WA ASSIGN WORK FROM SCHEDULE CLOSED TRAIN PLANNING PERSONNEL CLOSED
~
'03-020-02-TR APPENDIX 6 l
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Date: October 22, 1987 3 f Tz j' u ' V
SUMMARY
STATUS OF RESTART ACTION IN MCIAP
' DESCRIPTION DUE/ STATUS
' ISSUE / ACTION CLOSED 03-020-03-MA ASSIGN ALL PERSONNEL TO WORK-03-021 PROCUREMENT CONTROL CLOSED 03-021-01-ST TEMPORARY PURCHASING AGENTS' TEMPORARY UNIT CONTROL CLERK CLOSED-03-021-02-ST CLOSED 03-021-03-OR TEMPORARY. REPORTING STRUCTURE CLOSED 034 021-04-ST EXPEDITOR STAFFING RQRMTS i
03-022 PROCUREMENT INITIATION ! .\
CLOSED l 03-022-01-PU PDC'RELATED SPARES bD ~ ~ "
' S3_I$$_0$_SS_ .$$3IUS $3U ^"S_E "U"$[$_-_____________SS03-023 PROCUREMENT TRACIriG i
ESTABLISH MMAPPS TASK GROUP CLOSED 03-023-01-MM MMAPPS IMPROVEMENT PLAN CLOSED 03-023-02-MM INTERIM MATERIAL TRACKING CLOSED 03-023-03-MM CLOSED 03-023-04-MM MMAPPS TRAINING 03-024 MATERIAL HANDLING in ISSUE ESTABLISH STAGING FUNCTION CI.OSED 03-024-01-MM 03-024-02-MM MMAPPS USERS GUIDE 30-OCT-87 l
03-027 MAINTENANCE DATA BASE DEVELOPMENT INTERIM REVISION TO MR PROCESS CLOSED l 03-027-01-MA l EXPAND MR DATA BASE CLOSED
~
03-027-02-MA APPENDIX 6
'Date: October 22, 1987 r-)
M'
SUMMARY
. STATUS OF-RESTART ACTION IN MCIAP ISSUE / ACTION DUE/ STATUS
_______________________' ____ DESCRIPTION 03.-028 PREVENTIVE MAINTENANCE 03-028-01-PM SCHEDULE PREVENTIVE MAINTENANCE CLOSED i
03-028-02-PM PROGRESS PM WORK ITEMS ' CLOSED
~03-028-03-PM REPORT PM PERFORMANCE WEEKLY CLOSED
'03-029 MEASURING & TEST EQUIPMENT 03-029-01-CA INVENTORY M&TE COMPLETED '
03-029-02-ST ASSIGN TEMPORARY M&TE. STAFF CLOSED 03-029-03-MA ESTABLISH CENTRAL CONTROL OF M&TE COMPLETED i
i 1
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l APPENDIX 6
)
g' APPENDIX 8 EXECUTIVE
SUMMARY
A numerical summary of the status of action items undertaken in response to CAL NO 86-10 follows: l l
o Total items in Appendix 8:.................. 38 ,
l l
o Total items designated required for restart. 32 i 1
o Total items " COMPLETED":.................... 8 o Total items "CL0 SED":....................... 18 I 1
5-
/ em O
0
_ _. _ _-___________m_ _ _ _ _ . _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _.
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APPENDIX 8 -
1 STATUS OF CAL NO 86-10 ITEMS l This appendix consiste of those . items being . carried out to address.the commitments' contained in Boston Edison's-three-letter.
responses to -Cal No 86-10. For-convenience of review they are
- grouped by ' the. ' response letter from 'which they are drawn and L listed in the order that the commitments appear in the. letter.- ,
l Notations in the "DUE/ STATUS" are'used,as follows:
(DATE) Means that. work on the item'is not finished and the date indicates when-the actionis expected to be complete and ready.for senior management review.
. O' COMPLETED Means that the cognizant V
manager considers the
. results achieved satisfy the action requirements, <
but' that senior management is conducting-a' review before approving final closure of the item.
CLOSED Means that senior ?!
management review has been completed, the actions have received final approval and the documentation has been retained in an item closure file. ..
s, J
l
s I
l
()
r .Some actions are necessarily keyed to milestones and cannot be assigned a specific:date, but.are dependent upon the sequence of events surrounding that milestone. The status of such actions d
1 l
are indicated by the following conventions: j l
RESTART Means that the action is part of or'directly l tied to the actual reactor startup evolution :
or power ascension program.
RFO 8 Means that the action is scheduled as part of a the work to be done while the plant is shut j down for the next refueling outage. j (RS + ) Means that the action is scheduled for -
Restart plus some period - of ' time which will I always be e:: pressed in days. EXAMPLE: RS+120 1 means that the ' action is scheduled to be completed 1: O days after the reactor has been l started up. This convention may be used'with the other milestones in a similar manner, j EXAMPLE: RFO 8-60 means that the action is to be completed sixty days before the scheduled beginning of refueling outage number eight.
i O
I 23-Oct-87 j r3 l
(-) CAL NO. 86-10 First Response f DUE/ STATUS ACTION CLOSED 03-909-02 Reassemble, inspect and rebuild MSIVs.
l CdDSED 03-937-01 Investigate root cause and perform permanent modification of MSIV pilot poppets to ensure poppets remain screwed to poppet nuts during long term operation.
CLOSED 11-006-01 Develop a procedure to conduct a limited power ascent and descent through the portion of power ascension when the reactor mode switch is repositioned from run mode to start-up mode. This test may confirm the root cause analysis if anomalies recur.
CLOSED 03-909-01 Install GETARs to. monitor primary containment
/~' isolation system during comprehensive testing during next startup.
CLOSED 09-002-03 Evaluate and report MSIV leakage rates.
COMPLETED 04-005-04 Perform leakage test, across RHRs 68 check valves in accordance with Procedure 8.5.2.7 every refueling outage.
CLOSED 03-917-01 Install additional pressure gauges in RER system per PDC 06-30.
30-OCT-87 01-004-12 Develop RER nystem venting program. Include adequate vent location for local high points and a method to control venting frequency by venting results.
30-OCT-87 03-917-02 Provide means for system temperature monitoring.
COMPLETED 03-917-03 Remove pressure gauge installed on RHR injection p
X.)g APPENDIX 8
l l
23-Oct-87 line to allow for a vent path.
CLOSED 01-004-10 Revise alarm response procedure 2.3.2.1 on panel
'C903-left annunciator B-7 RHR high pressure alarm.
CLOSED 03-909-04 Replace Mode Switch with G.E. recommended model.
CLOSED 03-933-01 Write. PDC to install EPIC computer system.to I monitor the RPS and PCIS systems. J l
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O APPENDIX 8
i u
[
i F,- -! ._ 23-Oct-87 s_~) . CAL NO. 86-10 Second Responsa j l
DUE/ STATUS ACTION j i
CLOSED 10-001-04 Train operations staff on lu!R intersystem-leakage. 1 j
. issue.
CLOSED 11-005-02' Determine'the' test configuration andLthe.
acceptance criteria for test of pressure drop capability of the RERS 1001-68A and'68B check-valves.
COMPLETED --
Same action as CAL 86-10 First Response 04-005-04.
COMPLETED 04-005-03 1 schedule RHRs pressure gauge calibration every 1
. refueling outage.
31-MAR-88 03-917-16 After: trial--use as a temporary procedure evaluate-
-and change as required TP 86-85 and incorporate it 4
as a part of the RHE system operating procedure.
CLOSED 04-005-01 Place the RHR.high pressure alarm switches on a I once per cycle calibration schedule.
~
30-OCT-87 04-005-02 ,
Prepare and utilize a procedure-to periodically l' monitor RHRS pressures and. temperatures.
COMPLETED 11-005-01 Evaluate the feasibility of replacing or redesigning RHRS and Core Spray check valves to provide positive position-indication. '
RFO-8 03-917-15 schedule accomplishment of resultant design modifications on check valve position indicators, !
via the long term program.
- CLOSED 09-001-07 submit Technical specification change request to reduce frequency of MO 1001-28B and 29B valve stroking.
LO. APPENDIX 8 1
I w
1 23-Oct-87
- ;{
COMPLETED 03-909-06 Evaluate the loose neutral-wiring of RPS/PCIS system.
CLOSED' 03-909-05 Close out the following MRs t,o correct various circuit problems: 86-45-189, 86-45-190, 86-45-191, 86-45-192, 86-45-193,86-300, 86-301,86-302. j CLOSED 11-004-01 Resolve identified specific wiring and print discrepancies.
- CLOSED 03-917-04 Remove valve disk and evaluate or restore to i confirm the wear rate. !
RS + 120 03-933-02 Install EPIC computer system and have operable by startup to monitor the RPS and PCIS systems. ]
COMPLETED Same action as CAL 86-10 First Response 03-933-01.
() COMPLETED 11-005-03 conduct the pressure drop capability test of the j RHRS 1001-68A and 6BB check valves.
i 9
O APPENDIX 8
e t
23-Oct-87 CAL NO. 86-10 Third Response i DUE/ STATUS ACTION i
130-OCT-87 01-004-11 i
. Revise RHR system surveillance procedure'to
' ' include results and venting locations.
i'- . CLOSED 11-002-02
' Evaluate new RHRS and-core spray check valve position monitoring system options as an improvement over the original designs.
RESTART --
i Same action as CAL 86-10 Second Response 04-005-02. q 31-OCT-87 03-917-06 Retest the boundary: valves of the- RHR vessel 1 injection line for Appendix J criteria and for high pressure water leakage. Conduct: engineering H
evaluation of results.
.O crosto 11-oo2-o1 Revise safety evaluation'#1959 to clarify intent (address reduction in RER flow). !
30-0C7-87 01-004-09 Revise procedures to establish proper positions of.
the RHRS. isolation injection MO 1001-29A and B and MO 1001 28A and B valves. (Procedure. numbers 2.2.19, 2.2.86', 2.2.125, 8.5.2.2, 8.5.2.3, 8.5.2.6 and 8.7.1.4.1).
10-NOV-87 03-917-05 Local venting in RER to be performed once a week for four weeks per TP 86-84.
l RS + 180 --
Same action as CAL 86-10 Second Response 03-917-15.
m.
30 APPENDIX 8
t
'y\..
t APPENDIX-9 EXECUTIVE
SUMMARY
A . numerical Lsummary' ofL the status of. Management Meeting ' ' 86-41'
~
items follows:
o . Total items in Appendix 9:.................. 270 4
~
1 o Total items designated required for restart:.255 j q
Jo~ Total items " COMPLETED":.:................... 54 i o Total items " CLOSED":..........'............. 158 l
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-APPENDIX'9' g)y
'N
- STATUS OF MANAGEMENT MEETING 86-41 ITEMS This appendix is provided as a separate consolidation ' of .
Management Meeting 86-41 items, for ease of review by those
. concerned primarily with.that material.
This appendix' constitutes the third status summary of actions' !
undertaken by Boston' Edison to. address concerns presented during- j that meeting. The first two status reports were forwarded by l Boston Edison letters87-039 of 1 March 1987 and 87-070 of 6 May, 1987.
As explained in the forwarding. letter for. Revision 1 of Volume 2 l
'of the Restart Plan, future revisions to this appendix will d
j replace the status reports on this material which were previously.
submitted.by Boston Edison letter.
The information' presented here is grouped by the . same paragraph f numbers.used in. Attachment 1 to the NRC letter dated 31 December' j 1986, contains the actions taken to address specific concerns and i l
the status.of those actions.
Notations in the "DUE/ STATUS" column are used as follows:
(DATE) Means that work on the item is not finished and the date indicates when the action is expected to be. complete and ready for i senior management review. l
?
l
- COMPLETED Means that the cognizant !
action manager considers the results achieved satisfy the action !
requirements, but that senior management is '
conducting a review before approving final' i
L closure of the item.
- CLOSED Means that senior management review has i
been completed, the li actions have received final approval and the
~T documentation has been
. (V retained in an item closure file.
k l
M t- i; l
t
[~5 p )
-Q l Some actions are necessarily keyed'.to milestones and cannot be assigned a _ specific 'date, .but are dependent upon the sequence of events surrounding that milestone. The status ;
of such actions are indicated by the following conventions: i
- RESTART Means.that the action is part of or directly tied to the actual reactor startup evolution
-or power ascension' program. ,
1 RFO 8' Means that the action is scheduled'as part of i work to be'done while the plant is shut- !
the down'for the.next refueling outage. l (RS + ) Means Restart that'the milestoneaction is scheduled plus some period offor the' time.
V which .will always be expressed in ' days. l
~ EXAMPLE: RS+120 means that the action is :
scheduled to be completed.120~ days after the !
. reactor has been started up. This convention may be , used ' with the other milestones in a similar manner. EXAMPLES: RFO B-60 means that i the action is to be - completed sixty. days before the scheduled beginning of- refueling-outage number eight. ILRT+90 means that the
~ item is scheduled for completion ninety days
- d() after the completion of the-integrated leak rate test. i
(
o
l~.
L .
23-Oct-87 ]
5 NRC 86-41 SECTION. 1.A.1 l
Low Number of Licensed Operators DUE/ STATUS ACTION
. l CLOSED 01-001-07 ,
I Increase authorized complement of operators (total of equipment and reactor operators ) to 45.
31-DEC-87 01-001-09 .
Recruit and train licensed reactor operators to support a six section watchbill by the end of -l 1987.
CLOSED 01-001-10 Assign an experienced Watch Engineer to assist training.
)
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( APPENDIX 9
23-Oct-87
. NRC 86-41 SECTION 1.A.2 i
Lack of Staff. Support for Operations Department DUE/ STATUS ACTION {
l' CLOSED 01-001-01 Hire Operations section Manager.
1 CLOSED 01-001-03 Assign two operations Engineers'to the Chief I Operating Engineer as technical staff assistants. !
.I CLOSED 01-001-04 l Assign full time Planner to Operations Section.
CLOSED 01-001-05 l Transfer Shift Technical Advisor function to l
Operations.
[}
CLOSED 01-001-06 Fill'six BTA positions. ,
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l O- APPENDIX 9 I
I
---_-_A ___m_.-_.______ _._______ _
's i
j 23-Oct-87 NRC 86-41 SECTION 1.A.3 i
Worker Overtime Control.
DUE/ STATUS ACTION-CLOSED 01-002-01 Establish an overtime policy for all personnel.
Require that department manager's approval of work exceeding 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> / week.
CLOSED .01-002-02 Establish operation of a,real-time, computer-based ,
monitor to improve control of operator overtime ]
(including seven-day rolling average).
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APPENDIX 9
l
- 23-Oct-87
.NRC 86-41 SECTION 1.A.4
^
i i
Unreadable Station' Drawings DUE/ STATUS ACTION CLOSED 06 L 003-01 Publish drawing legibility standards. '!
CLOSED 06-003-02 Implement a, quality check of all new vendor
' drawings and reject illegible drawings.
CLOSED 06-003-03 Upgrade existing drawings as drawing revisions occur.
CLOSED 06-003-04 o['*) Examine prints madeLfrom all existing aperture
\"2 cards and identify poor quality eperture cards and poor quality original prints.
CLOSED 06-003-05 Prioritizing poor quality original drawings for restoration, q l
+ . 3 CLOSED 06-003-06 Prepare plan and schedule for drawing restoration work. j CLOSED 06-003-07 )
Upgrade quality of all equipment in the drawing j I
processing cycle. J CLOSED 06-003-08 Implement 100% quality inspection of new aperature cards sent to the Document Control Center.
(
APPENDIX 9
- m. ___ _ _ . _ _ _ _ _ _ _ _ _
n t
2 3 -Crct-87 :
}
NRC,86-41 SECTION 1.A.4 CLOSED '06-003-09 Train clerical staff in drawing legibility.
requirements.
Ck,OSED 06-003-10 .
Issue Work instructions and initiate monthly . l random' sampling of DCC issued drawings.to monitor operator and equipment performance.
4
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i O APPENDIX 9 l
1
.1 l
23-Oct-87 J NRC 86-41 SECTION 2.A.1 Continuing Weakness in Follow-up to Radiological Problems i
DUE/ STATUS ACTION CLOSED 02-008-01 Upgrade Radiological Occurrence Report (ROR) 'q procedure to improve categorization of ROR's by severity level.
f CLOSED 02-008-02 Assign a full time ROR coordinator. !
'i CLOSED .02-008-03 ;
Assign'where possible ROR's to Group Leader level !
or above. j
- u.
CLOSED C2-008-04
\ Establish a computerized ROR tracking system. . !
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O APPENDIX 9 i
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a L !
n !
l L 3f
,z 23-Oct-87 NRC 86-41 SECTION 2.A.2 ;
L Worker Attitude Towards Radiation Protection.& Accountability 1-
'DUE/ STATUS ACTION CLOSED 02-007-01 Develop ~ALARA program procedures.
.i.
. CLOSED. 02-007-02 Establish radiation exposure. goals and track'and y report results. .
CLOSED 02-007-03 ,
Revise annual performance evaluation form toL include ALARA performance.
CLOSED 02-007-04 Determine that the radiation exposure goals are O effective.
l' CLOSED 02-007-05 ;
Implement a continuing program to identify better !
methods (including the purchase of additional i equipment) to minimize, control and remove <
contamination. !
COMPLETED 02-007-06 l Monitor effectiveness of purchased devices by tracking the number of times such devices are used and its effectiveness in controlling the spread.of I contamination. Use this effectiveness monitoring l to identify better methods, as needed.
i COMPLETED 02-007-07 Establish Nuclear Operating Manager as chairmen of ALARA committee.
RESTART 02-007-08 Monitor effectiveness of the ALARA program by APPENDIX 9 i
1 O .
'T ,
23'-Oct-87 TY ]
Q 2.A.2 NRC 86-41-SECTION closely tracking collective station exposure and- '!
I
-by assessing the effectiveness of the ALARA committee and its recommendations.
CDOSED- 02-007-09 Establish an ALARA Employee of the Month award for achievements in exposure reduction. -
COMPLETED 02-007-10' Complete training on-ALARA program and1 fully-implement the program.
CLOSED 02-009-01
' Involve Line Managers in routine reinforcement of radiological requirements.
CLOSED . 02-009-02 Reassign responsibility for implementing disciplinary action for radiation protection
) violations from Radiological Section Manager to j
^ individual supervisors.
CLOSED 02-009-03 Revise GET program to emphasize that the. basis for radiological protection is to ensure the health j and safety of individual workers. t l
CLOSED 02-009-04 conduct formal training programs in contamination control techniques for operations, maintenance and radiological supervisors, workers and technicians.
I i
O APPENDIX 9
9 6
'T 23-Oct-87 (O .
NRC 86-41 SECTION 2.A.3 i
Implementation & QC of New' Environmental TLD Program DUE/ STATUS ' ACTION CLOSED 02-010-01 Replace existing environmental TLD system by Panasonic Environmental TLD System.
CLOSED 02-010-02 Implement procedures _to send Panasonic
~
Environmental TLDs to an independent laboratory-for irradiation on a quarterly basis.
CLOSED 02-010-03 Continue to participate in-the International Environmental Dosimeter Intercomparison Project.
CLOSED 02-010-04 Develop a QA procedure for the nr.el Environmental TLD System program.
CLOSED 02-010-05 l Evaluate Environmental TLD program effectiveness i using TLD intercomparison studies.
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APPENDIX 9
l l-1 l
I 23-Oct-87 l
's l
NRC 86-41 SECTION 2.A.4 l
l l Communication Between Health Physics Group & Other Licensee Depts l
DUE/ STATUS ACTION CLOSED 02-001-03 Assign Health Physics Coordinators to the maintenance section for groups which have. work.
loads which require substantial numbers of i Radiological Work Permits. .
i' 30-OCT-87 02-003-04 .
Section Managers include in plant tours observations of communications between the i
l Radiological Protection Section and other' station l sections.
1 1
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. 1 1
j APPENDIX 9 !
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T p; f 23-Oct ,. ;,
NRC,86-41"SECTION' 3.A.1 em , ,
- s Maintenance supervision staffing vacancies i
. }'
DUE/ STATUS ACTION ]
.. 1 CLOSED- 03-901-01
. trill existing supervisory vacancies.
4
-)
COMPLETED; 03-901-02 ..
Computerize administration of overtime control.
CLOSED 03-901-03 Establish and staff a Procurement-Eupport' Group l
(PSG) to facilitate processing of procurement .l documents. ;
CLOSED 03-901-04
~% Develop a centralized planning and scheduling 1 (d
' function.within the Maintenance Group to directly support the. individual maintenance. disciplines.
CLOSED 901-05 '
Hire three additional maintenance. staff engineers.
CLOSED 03-901-06 Rire.one HVAC supervisor.
i CLOSED 03-901-07 ,
Establish apprenticeship progrEn in the three
~
maintenance disciplines with twalve apprentic'e g
-positions approved.
E COMPLETED 03-901-08 Accelerate the process of filling open Maintenance ;
supervisory positions.
l LO APPENDIX 9 L
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'23-Oct-87 1
f, HRC 86-41 SECTION 3.A.1
- o m
., i RS +-90; ,
03-901-09 ..
- j. Evaluate-long-term Maintenance section' staffing
' / , v r.
y.{ plan.
y .
CLOSED ' 03-901-10 Establish management tours to assess the y effectiveness of supervisors in enforcing high standards.
l f
REST' ART 03-906-02' Improve' Maintenance Group performance trending.
system and include ways to identify and correct ,
-(
areas of. weakness.
CLOSED 10'0C'3-01 Develop, issue and-use training module for field supervision / monitoring activities.
L
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APPENDIX 9 l
__________-_____-_-__-Q
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/ '23-Oct-87 NRC 86-41 SECTION 3.A.2 '
j.
Limited Mainten'ance - Operations Interface c- , . ,.
DUE/ STATUS h' ACTION'
<r' ,
I- CLOSED 1 03-903-02 Establish a met. Sod to prioritize MRs and inform _ M affect ed departments of results. ./
t
.;> / . v '
CLOSED 03-903-03 Establish a plan-of-the-day work prioritization which includes all disciplines related to the C approved schedule. >
CLOSED I 03-903-04 '
Attend industry conference on '
maintenance / operation interface.
O CLOSED 03-903-05 4 Estr.L11sh an MR feedback system to enstire that the cognirant organization is informed if the MR will
not be worked as planned.
i )
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/
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/
l APPENDIX 9
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1 1
23-Oct-87
- ('s) 1
, NRC 86-41 SECTION 3.A.3 l q
Implementation 'of Maintenance Planning Group (Backlog Disposition) i DUE/ STATUS ACTION CLOSED 03-901-17 j Improve the rate of reducing outstanding ,
maintenance backlog by increasing contractor work l force (including engineers, supervisors and i craft). ]
I CLOSED 03-902-01 Establish' maintenance planning group with full
' time planners. . q CLOSED 03-902-02
- Centralize maintenance planning and scheduling activities.
CLOSED 03-902-03 )
Develop weekly planning / scheduling effort for I routine maintenance activities. )
I CLOSED 03-902-04 !
Correct the data contained in the administrative ]
control system for MRs. l l
COMPLETED 03-902-05 '
Coordinate maintenance activities between the various disciplines through weekly planning .-a4 scheduling meeting. 4 CLOSED 03-902-06 Implement new maintenance manual to provide guidance for conduct of planning / scheduling effort. ,
f CLOSED 03-902-07 Restructure maintenance group to provide increased
{}
APPENDIX 9 l
l a
1 Oct-87 j
, NRC 86-41 SECTION 3.A.3 management attention to.both outage-related
^]
maintenance and backlog.
. e
]
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4 LO- ,
O APPENDIX 9
{
k 23-Oct-87 NRC 86-41 SECTION 3.A.'4 i
? Formalization E' Implementation of Preventive Maintenance Program 1
DUE/ STATUS ~ ACTION i
CLOSED 03-905-02 I
Update preventive maintenance tracking list.
CLOSED- 03-905-03 Have maintenance planners schedule PM activities and incorporate reviews and update-status.-
,_ _. j I
COMPLETED 03-905-04 The Compliance Group shall issue variance reports 1 on PM activities in accordance with the j procedure. i COMPLETED 03-905-05
[~)
' Clarify procedural requirements and. increase effectiveness of tracking list by revising PM tracking procedure;-increase management' attention 107 notifying responsible group leader of failure to perform a_PM. Elevate to Section Manager attention upon third consecutive non-performance.
CLOSED 03-905-06 Trend PM performance for each discipline in the maintenance group. ;
l CLOSED 03-905-07 Develop and issue PM procedures for Limitorque motor operated valves.
f I
i 01-MAR-88 03-905-08 !
Evaluate the failure analysis reports of motor operated valve failures to determine the adequacy of the failure analysis reports. j C:) 1 APPENDIX 9 l l
W i
v 1 1
l 23-Oct-87 NRC~86-41.SECTION 3.A.4 j I
' CLOSED 03-905-11 Develop and issue PM requirements for Limitorque motor operated valves.
26-OCT-87 03-920-08 Review motor-operat'ed valves for inconsistent sizing and oversizing of motor overload devices.-
4 I
CLOSED 10-003-02 Conduct training and continuing education of maintenance personnel assigned to work on Limitorque MOVs.
1 i
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O APPENDIX 9 I- _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ -
23-Oct-87 NRC'86-41 SECTION 3.B.1 ATWS Recirculation MG Set Field Breaker Failures DUE/ STATUS ACTION CLOSED 03-929-01 Perform root cause analysis of ATWS RECIRC MG set field breaker which failed in June 1986.
CLOSED 03-929-02 Perform root cause analysis of recurring breaker failures.
CLOSED 03-929-03 Conduct formal industry survey of failure history and corrective action.
CLOSED 03-929-04 Perform aging and testing of lubricant.
CLOSED 03-929-05 Investigate design change options (initiation of drive motor trip on ATWS signal - redundant to field trip; change spring design field breaker).
CLOSED 03-929-06 Investigate and recommend possible improvements to maintenance and testing practices.
RFO-8 03-929-07 Update breaker maintenance manual / procedure to define use of special lubricants and enhance steps for making breaker adjustments.
CLOSED 03-929-08 Update root cause analysis and risk and reliability analysis relating to recirc MG set trip breakers.
O APPENDIX 9
1,"
d l '23-Oct-87
'NRC 86-41 SECTION 3 . B .1 ~
CLOSED 03-929-09 Reassess corrective ~ action to decide whether replacement of the:recirc MG set field breaker ,
would be more prudent than continuing trouble
- shooting and repair efforts.
I RESTART 03-929-10 j Install PDC 87-30 to upgrade recirc MG set trip j breakers.
. COMPLETED 03-929-11 Implement improvements to maintenance and testing
' 5-~ practices recommended by Nuclear Engineering Department investigation.
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APPENDIX 9
II l L1 l h
1 0 23-Oct-87 O1 I- NRC 86-41 SECTION 3.B.2 Breaker Setting & Coordination Implications of the Safety Bus B10 l i
.DUE/ STATUS ACTION !
l
, CLOSED 03-931-01 l
-Initiate a temporary modification to correct i immediate breaker coordination problem which was not addressed in the original design.
i CLOSED 03-931-02 1 Initiate a full review of the breaker coordination 4~~ issue.
.j CLOSED 03-931-03 Develop a new and more comprehensive design basis.
t RESTART 03-931-04 !
Implement required PDC 87-15 changes.to resolve i breaker coordination issue. !
COMPLETED 03-931-05 .
Implement a Temporary Modification to correct i immediate breaker coordination problem which was not addressed in the original design.
.i f
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- U APPENDIX 9 1
1 j ]L e 23-Oct-87:
A.J.
NRC 86-41 SECTION 3.B.3 I
Minimum Flow Protection for RER Pumps d l
DUE/ STATUS ACTION CLOSED 03-919-01 Revise safety evaluation for existing PDC 86-95 to-establish minimum flow design Lasis, revise PDC 86-95'accordingly.
COMPLETED 03-919-02=
Correctly install orifice plate in RER minflow
- ~ line. 4 CLOSED 03-919-03:
Review RHR minflow operating logic and issue appropriate design changes.
RESTART 03-919-04 Install PDC 86-33 (MO 1001-18 AEB).
J l
RESTART 03-919-05 Install PDC 86-95 to establish minimum RHR flow.
l l
1 j
i APPENDIX 9 I
'/
I p~; ; r 23-Oct-87 NRC 86-41 SECTION 3 . ]B . 4 1
Cracked Welds & Loose Bolts in Low Pressure ECCS Systems DUE/ STATUS ACTION. l COMPLETED 03-906-03 Review FEMR trend analysis to determine whether MCARs would'be applicable / appropriate to address root cause of cracked welds and loose bolts in low pressure ECCS systems.
COMPLETED 03-906-04 5~ Implement corrective action training for NED personnel. ,
i l
CLOSED 03-916-02 . .
Review previous action taken on failure analysis I for cracked welds and loose bolts in ECCS.
(:) l CLOSED 03-916-03 Investigate root cause of weld failures.
CLOSED 03-916-04 Perform root cause evaluation for bolt failures.
C7MPLETED 03-916-05 Install replacement yokes.
RFO-8 03-916-06 Implement corrective actions to address root causes of weld failures identified in Action Number 03-916-03.
l O APPENDIX 9
l
~
23-Oct-87 NRC 86-41 SECTION 3.B.5 Core Spray Check Valve & MOV DUE/ STATUS ACTION
' CLOSED 03-920-01 Evaluate scope and root cause of problem of core spray test check valve internal disc becoming ,
disassociated from the swing lever arm.
i
-COMPLETED 03-920-02 Confirm no similar vertical installation.
CLOSED 03-920-03 Install new discs including anti-rotation pins in disc of susceptible check valves temporarily until new discs with anti-rotation stops and improved materials are installed.
t RESTART 03-920-04 !
verify continuing valve operability (Cv1400-35 and !
214) through routine system surveillance. j RFO-8 03-920-09 If necessary, implement the physical change and/or configuration necessary to resolve check valves designed for vertical service or reconfigure existing check valves for horizontal use.
i, I
i APPENDIX 9 1
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f i
23-Oct-87
[d) i l
NRC 86-41 SECTION 3.B.6 l Heat Damage to Primary Containment Isolation System Cabling 1
DUE/ STATUS - ACTION COMPLETED 03-930-01 ,
Review operation of circuit involved and evaluate l extent of damage.-
i COMPLETED 03-930-02 f Replace cable, relocate conduit and repack valve 1 3-- HOO100-107.
CLOSED 03-930-03 )
Reinstall insulation on valve and affected steam l lines. J
() COMPLETED 03-930-04 Include in training an emphasis on.importance of early identification and correction of material deficiencies.
COMPLETED 03-930-05 Assess effectiveness of foregoing actions through continuing program of FEM trend analysis. ,
l
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APPENDIX 9 ;
l
_-_------_--_-_-_-__J
l 23-Oct-87
, NRC 86-41 SECTION ' 3. B . 7-
- )
Secondary conta'inment Damper Failures i
DUE/ STATUS ACTION '
I CLOSED 03-914-02 Identify and document root cause for secondary containment damper failures.
CLOSED 03-914-03 1 Develop list of secondary containment dampers 1 affected.by root cause.
COMPLETED 03-914-04
-Replace secondary containment dampers. 2
\
(~)h v
)
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6 O- APPENDIX 9 l l
l 1
(
/'i 23-Oct-87
. ig NRC 86-41 SECTION 3.B.8 salt serviceLwater Piping Corrosion
-DUE/ STATUS ACTION CLOSED 03-924-01 Establish' scope of problem.
CLOSED 03-924-02 Perform root cause study of SSW corrosion in screenhouse and buried piping.
.g __
RESTART 03-924-03 .
Replace salt water components as necessary per PDC 86-22. Install test material piping piece in screen wash piping.
~*
COMPLETED 03-924-04 ]
-]%-- Investigate integrity of salt water pumps. j COMPLETED 03-924-05 Investigate integrity of salt water pipe including ,
screen wash piping. j RFO 60 03-924-06 l Provide inspection criteria for routine inspections, 2 months before RFO-8.
CLOSED 03-924-07 Issue design change modification to replace / repair degraded components.
RFO-8 -180 03-924-08 Identify improved materials for asW service 6 months before RFO-8.
20-NOV-87 03-924-09 {
Investigate cause of incorrect status report for APPENDIX 9
1
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~
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23-Oct i87
- O..
NRC 86-41 SECTION 3.B.8
?
ssW piping and implement corrective action, j
.1 CLOSED 03-924-10 Repair / replace degraded components.
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-O APPENDIX 9
- - - - _ _ _ _ _ _ _ _ k
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i
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23-Oct-87 l
- L.)s NRC 86-41'SECTION 3.B.9 I
-l d
Potential Corrosion of Primary. containment Isolation; Valves j DUE/ STATUS ACTION )
CLOSED 03-925-01 -
Develop list of Clow corporation butterfly valves ]
(wafer type) that are used'at PNPS.
l l
COMPLETED 03-925-02 Examine one of the eight Clow valves and review j results with the valve vendor, and respond to ESR ]
4 ~~
87-590. j RESTART 03-925-03 continue normal monitoring of valve operation i during.LLRT and valve timing tests, j l
I) 1 1
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(~)
APPENDIX 9 l
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1 23-Oct-87 !
.n ss NRC 86-41 SECTION 3.B.10 1 9
Design Deficiency in Intermediate Range Neutron Monitor Power Supply DUE/ STATUS ACTION CLOSED 03-910-01 Evaluate SIL 445, INPO SER and GE RIC SIL 007 for application to PNPS IRM designs. !
i RESTART 03-910-02 l Functionally test IRMs. i RESTART- 03-910-03 Increase existing fuse capacity by 100%. .
CLOSED' 03-910-04 Evaluate SIL 445 recommendation to add voltage i sensing relays.
APPENDIX 9
i.
23-Oct-87
)
NRC 86-41 SECTION 3.B.11 Residual Heat Removal & Core Spray Pump Inspection Results l 1
6 DUE/ STATUS ACTION COMPLETED 03-917-09 Disassemble, inspect and conduct preventive maintenance program on RER pumps. l l
r CLOSED 03-917-10 ;
Replace RHR pump impeller wear rings. !
CLOSED 03-917-11 "
j visually inspect RHR pump wear rings for cracking. ;
CLOSED 03-917-12 Conduct metallurgical evaluation of RHR pump ,
impeller wear rings. )
CLOSED 03-917-13 !
Transmit results of RHR and core spray pump inspection to NRC.
CLOSED 03-917-14 J Disassemble, inspect and rebuild core spray pumps.
)
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i O APPENDIX 9 I
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l 1 2 3-Oct--8 7 (a -
NRC 86-41 SECTION 3.B.12' l
l l
Design Deficiency in the Standby Gas Treatment (SBGT) Systems !
DUE/ STATUS ACTION I
COMPLETED 03-926-01 Correct SBGT' deluge system to preclude inadvertent actuation. Modify SBGT to eliminate remaining design deficiencies.and single active failureof including SBGT heaters monitoring for failure. 3 a i i
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l APPENDIX 9 l
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i 23-Oct-87 .l
/(_3
/ - j NRC 86-41 SECTION 3.B.13~
' Potentia 1' Concrete Wall Issue DUE/ STATUS ACTION 1
CLOSED 03-927-01 Contact the original PNPS contractor for a search-of construction records to establish that reinforcing bars were installed in safety related concrete walls in accordance with design drawings.
i CLOSED 03-927-02 Use experience in mapping embedded steel reinforcing bars in concrete walls and in drilling for expansion anchor installation to validate design drawings for concrete walls.
O O.
APPENDIX 9
__ _-___.m.-2._m__.___ __
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o, 23-Oct-87 l
\
NRC 86-41 SECTION 3.B.14 Design Deficiency in the HPCI Turbine Exhaust System DUE/ STATUS ACTION CLOSED 03-915-01 Perform root cause analysis of HPCI turbine exhaust water hammer problem.
l RESTART 03-915-02 Implement HPCI exhaust line vacuum breaker upgrade, r
RESTART 03-915-03 Conduct post construction operability testing'to i verify HPCI turbine exhaust modification '
effectiveness.
I I
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I i-(2) APPENDIX 9
l 1
23-Oct NRC 86-41 SECTION 3.B.15 Loose' Wiring
' DUE/ STATUS ACTION ,
COMPLETED 03-909-06 i Evaluate the loose neutral wiring of RPS/PCIS system. ;
J l CLOSED 03-909-07 Identify prior similar termination problem events.
_(similar to loose neutral wiring of Action Number 909-06).
COMPLETED 03-909 Analyze termination deficiency events.and recommend corrective actions. concerning-loose wire problems.
RESTART 03-909-09 h Revise Station procedures requiring removal of i fuses in performance of tests and specify_ method of' checking fuse tightness. '
COMPLETED 03-909-10 l
~
Investigate applicability of new incipient failure i detection' techniques to provide early detection of loose wires and termination deficiencies. i I
COMPLETED 03-909-11 Assess the effectiveness of the correction of electrical connector tightness problems. Monitor FEMR reports to determine trends.
6 e
APPENDIX 9
3
~
]
23-Oct-87' NRC 86-41 SECTION 3.B.16 )
)
Use'of Fuses & Metal Links ~in Control Circuits I DUE/ STATUS- ACTION RS + 270 03-913-01 l Determine where links are used in safety related j motor control circuits. g l
CLOSED 03-913-02 . .. i Perform Engineering evaluation to replace metal links with fuses in Appendix R related' motor ;
'~~~
control circuits. j j
RS + 270 03-913-03 1 I
Correct drawings to reflect fuses / links based on walkdown/ Engineering evaluation.
RESTART 03-913-04 Implement plant ~ design changes (based on u Engineering evaluation 86-41-3.B.16-2.1) to replace Appendix R related metal links.
RS + 150 03-913-05 .
Perform engineering evaluation to replace metal !
links with fuses in non-safety related motor control circuits.
RS + 270 03-913-06 Implement plant design changes (based on Engineering evaluation 86-41-3.B.16-2.1) to L
replace non-safety related metal links.
RS + 150 03-913-07 Review non-safety related motor control circuit drawings for metal links that require replacement l with fuses.
l O APPENDIX 9 1 j
23-Oct-87 NRC-86-41 SECTION 3.B.17 seismic Qualification of HGA Relays DUE/ STATUS- ACTION 02-NOV-87 03-928-02 Identify HGA relays in use in safety related
. applications.
CLOSED- 03-928-03 Evaluate safety significance of HGA relay j installations, and issue design change
'~~ modification to replace unacceptable relays with qualified substitutes. ;
CLOSED 03-928-04 ,
Replace unacceptable HGA relays with qualified substitutes.
O !
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APPENDIX 9
k
.,} (~ 23-Oct-87 i NRC 86-41 SECTION 4.A.1-surveillance scheduling Weaknesses DlTE/ STATUS ACTION 30-NOV-87 04-001-01 Centralize the control of the surveillance data base and future changes within the Technical section. The surveillance Test Program will be managed by the Technical section systems Group Leader.
15-DEC-87 04-001-05 Revise the MSTP based on INPO Good Practice TS-410 to address missed surveillance tests, conflicting definitions of once/ cycle, inability of the surveillance tracking system to compensate for plant mode or for multiple component testing and clarification of line responsibility.
.R V
COMPLETED 04-001-06 Identify and suggest corrective actions to problems with surveillance requirements resulting from ambiguous' operating cycle related to Technical specification surveillance requirements.
30-NOV-87 04-001-07 -
Improve and simplify MSTP database.
15-DEC-87 04-001-08 Train personnel on new MSTP program and l procedures. !
20-OCT-87 04-001-09 Direct the implementation of procedural changes to address ambiguous operating cycle relative to Technical specification surveillance requirements identified by surveillance requirement study.
1
}
APPENDIX 9
i 23-Oct-87 NRC 86-41 SECTION 4. A. 2-ECCS Test Adequacy.
DUE/ STATUS . ACTION H RESTART 007-01 Revise a3 necessary ECCS Logic System functional tests and_ procedures required for various mode.
switch positions.
1 l
15-NOV-87 04-007-02 Determine adequacy of simulated automatic
,_- actuation testing approach.
RESTART 04-007-03 Revise simulated automatic actuation. testing to' incorporate the recommendations contained in the-evaluation of adequacy. report.
- RESTART 04-007-04 Make appropriate ECCS Logic System functional test procedure changes-to' incorporate simulated automatic actuation testing.
t I
r
() APPENDIX 9 m_____.____m__ 2. _-___. _____ _.
hI i' i 23-Oct-87 l
.i tT i:. 1 NRC 86-41 SECTION 4.A.3 1
.i.
Calibration.& Testing'of Protective Relays & Breakers
,DUE/ STATUS ACTION CLOSED 04-005-06 .
Evaluate' protective relayesetting and test
. criteria.and provide written criteria to the .]
Maintenance Section. .,
k CLOSED 04-005-07 . ,
Revise and update controlled docurants for all 4KV r- circuits and 480V load centers to reflect protective relay / breaker setting and testing.
]
RS + 60 04-005 i08 Revise and tpdate controlled' documents for all ,
(480V motor control centers to reflect protective relay / breaker setting and testing.
u o '
l
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li
)
I APPENDIX 9
- l 1
,t i
t !' i
- r. n 23-Oct-87
., NRC 86-4 b3ECTION - 4. A. 4 ~
yp , ,
a 1
-.-_. :)
' Control of Measuring & Test Equipment (M&TE) t -DUE/ STATUS ACTION COMPLETED- 04-006-01 Establish central M&TE issue areas for each. g discipline within maintenance. l j
. i COMPLETED C4-006-02 J I
Segregate out.of calibration METE equipment from other METE equipment to prevent inadvertent use.
4 COMPLETED 04-006-03 l
, ,, Assign maintenance staff to manage the M&TE issue areas.
, ]
i CLOSED 04-006-04 q
.() Station management spot check METE equipment through implementation of the management monitor l Watch Program.
I i
20-NOV-87 04-006-05 Formalize a program for assessing the ;
effectiveness of METE' control using plant i management' tours emphasizing that function. i
, i 31-OCT-87 04-006'-06 Evaluate the effectiveness of METE control using a program of M&TE audits.
i t
\\
j APPENDIX 9
3- ,- -.y-, . , .
' ~
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- p. <j !,< 23-Oct-87: ,
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NRC 86-41 SECTION 4.A.5 #
,.a .e' y- i j
^
> ~1 2 a Loca]. Leak Rate Test-(LLRT) Program Administration s' ,
(
t dub'/ STATUS ACTION CLOSED 04-003-01 fa-Submit a letter to.the NRC requesting a -
clarification of the two year interval set forth 9 in 10CFR50 App. J " Containment Leakage Contdl.f'. '
)
3 ,.i 3 11 y ;, >,
$ ,$ ., l CLOSED ,' '(j'Of-QO3-02 . .
> /
i ', , 'two^ year maximum test interval will be established r- , ' /; for o ch LLRT compor.ent and included in master surveillance tracking program until clarification
'4 7 'is job',ained. ,,
,e
- ).
- ,',i u.
j .i a CLOSED ' ' > 04-003-03 )
i~
I
'Upd6te_MBTP to include all cor.ponents requi2.ing
'J ,ULRT and insure two year maximum interval between
( ' testi of each' 'compontant; is properly controlled.
8
,y RESTART 04-003 Complete LLRT Surveillance Tests for LLRTs that excoed the two year requirement.
i RS + 150 04-003-13 ,
submit-a Technical specification change request to ,
clar(fy the definition of'once per operating /
cycle.s ' , ' i i !> ;
)
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9
' i APPENDIX 9
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j
23-Oct-87 NRC 86-41 SECTION 4.B.1-Recurrin'g Local Leak Rate Test Failures
, DUE/ STATUS ACTION ep
'? ' CLOSED 04-003-06 Establish an LLRT Failure. Analysis Team as a standing entity to' conduct root'cause analysis and make recommendations to correct problems and prevent future failures.
ILRT.+ 90 04-003-07 r- Analyze cause of leaking containment Isolation valves and develop corrective / preventative
. maintenance actions.
- CLOSED 04-003-08 Revise the LLRT Surveillance Procedures to add a precaution regarding prior approval and
() documentation of test connection valve packing adjustments. j I
COMPLETED 04-003-09 Initiate a valve Betterment Program to upgrade j valves that have a history of maintenance or spare parts availability problems.
()
RESTART 04-003-14 Implement the corrective / preventative maintenance actions developed by the Valve Betterment Team and
. approved by management to correct the cause of l leaking containment Isolation Valves. l l
I
['
- (~)\ APPENDIX 9
l t 23-Oct-87
' )
NRC 86-41 SECTION 5.A.1
, Emergency Action Level Review DUE/ STATUS ACTION CLOSED 06-005-01 Review EALs-against NUREG-0654.
CLOSED 06-005-02 Revise Procedures 5.7.1.1, 5.7.1.2, 5.7.1.3, 5.7.1.4 and 5.7.1.5 to comply with NUREG-0654.-
3__
CLOSED 06-005-03 Revise lesson plans as necessary for operator training on EALs.
CLOSED 06-005-04
(~s Condu=t operator treining on revised EAL V procedures.
COMPLETED 06-005-05 Revise,. print and distribute wall mounted EAL )
displays. 1 1
O APPENDIX 9 I
- _ - _ - - _ _ _ _ - _ _ \
23-Oct-87 ;
r ("T
~ '
lERC 86-41 SECTION 6.A.1 Continuing Weaknesses in Following-Up on Problems DUE/ STATUS ACTION CLOSED 07-001-02 Establish Security Operations Group.
CLOSED 07-001-03 Add one BEco Security. Supervisor per shift. ;
CLOSED 07-001-04 i
Establish Administration, compliance and. Technical specialist positions and fill positions with 3 I
permanent BEco employees.
t CLOSED 07-001-05 Establish three new supervisory positions in the f-(_gj plant areas of Main Gate Access, Central Alarm Station and Secondary Alarm Station.
COMPLETED 07-001-06 Increase the total security force.
COMPLETED 07-001-07 Reduce the supervisor-to-patrolman ratio from 1-20 to 1-10 or less.
COMPLETED 07-001-08 Perform root cause analysis of continued weaknesses in follow-up on problems.
,, 30-OCT-87 07-003-01 Review and update / revise security procedures and instructions.
l; APPENDIX 9
23-Oct-87
.O-
NRC 86-41 SECTION 6.A.2 I
Prioritization'of Security Maintenance 1 I
i DUE/ STATUS. ACTION COMPLETED 07-002-01 conduct a system level requirements analysis to identify improvements required in the hardware.
CLOSED 07-002-03 Monitor the material status of the security system. A security staff technical specialist ,
5- will track the outstanding maintenance items, !
monitor preventive maintenance and surveil, lance status and establish the primary focus for major modifications of the security systems.
COMPLETED 07-002-04
<S Prioritize the Security maintenance requests.
s_)
I Establish controls to ensure proper prioritization
-of future security maintenance requests.
25-OCT-87 07-002-07 Develop a security equipment preventive maintenance program.
i; l.
4
($) -
APPENDIX 9 I
. 23-Oct-87 NRC 86-41 SECTION 6.A.3 Termination of the Use of Long Term Compensatory Measures DUE/ STATUS ACTION' COMPLETED 07-002-08 Conduct an evaluation of the continual utilization of compensatory measures.
COMPLETED 07-002-09 Increase management's awareness of the use of .
compensatory measures. I 3_ _
COMPLETED 07-002-10 Discuss with the responsible individual.any compensatory measures in existence greater than'30 days to ensure resolutions are promptly planned ,
- and scheduled.
A
! 5,_)
CLOSED 07-002-11 Inform NRC of new dates on installation plans for security modifications.
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1 es g APPENDIX 9 i
l 23-Oct-87 NRC 86-41 SECTION 7.A.1 Fire Brigade Training DUE/ STATUS ~ ACTION CLOSED 05-001-01 Centralise Fire Protection function at site through establishment of.new group leader position '
to provide centralized management of the Fire Protection program including direction of resources, budget planning and control and long-term planning of the program.
7 CLOSED- 05-005-01 Hire permanent BECO Fire Brigade Instructor.
CLOSED 05-005-02 Revise Nuclear Training Manual requiring mandatory
( quarterly attendance at. fire brigade training.
(
CLOSED 05-005-03 Establish two drills per member each year, as requirement for fire brigade membership.
CLOSED 05-005-04 Establish and maintain Fire Brigade qualification files.
23-OCT-87 05-005-05 Provide written scenarios to Fire Brigade Leader for drills.
CLOSED 05-005-06 Conduct critique at and of each drill.
CLOSED 05-005-07 '
it Revise the Fire Brigade Yraining Drill Procedure to evaluate the performance of the participating 4 brigade members as a team. l APPENDIX 9
l i
f.
23-Oct-87 -l rs. . i tj NRC 86-41 SECTION 7.A.1
-CLOSED 05-005-08 Perform-QA audit to-assure the Fire Brigade
' Training is being implemented in accordance with approved procedures.
Y e-O h
11 APPENDIX 9 i
T 1
23-Oct-87 O
'- NRC 86-41 SECTION 7.A.2 l
Inadequate'Use of Corrective Action Program i
DUE/ STATUS ACTION l l
CLOSED. 05-006-05 Train appropriate station and engineering .l personnel in existing corrective action program 'l including use of P&MRs. l CLOSED 05-006-06 !
Assess effectiveness of Corrective Action Program !
's-- Training, (specifically FEMR use) using performance indicators. ;
CLOSED 05-006-07 Establish a Fire Protection Coordinator to assist Barrier Walkdown Team and Watch Engineer in identifying Fire Watch postings for identified
.(g) deviations.
APPENDIX 9
_____z_________. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 1
l 1 L
jest 23-Oct-87
\% I. .
NRC 86-41 SECTION 7.A.3 Prioritization of Fire Protection Maintenance DUE/ STATUS' ACTION i CLOSED 05-002-01 Inoperative Fire Protection systems requiring compensatory measures are incorporated into the
- plan-of-the-day.
COMPLETED 05-002-02
,_. Inoperative systems requiring compensatory measures receive daily review and are assigned a
. priority level. .
CLOSED 05-002-03 Inoperative systems requiring compensatory measures receive priority treatment in the
{ Plan-of-the-Day meetings. -
CLOSED 05-002-04 Establish fire watch compensatory measures action items report to assign ownership of problem ;
solutions.
COMPLETED 05-006-01 Use routine submittals from the Fire Protection Group and the Plan-of-the-Day process to establish priority treatment of Fire Protection Maintenance Requirements.
CLOSED 05-006-02 Establish a fire protection system status board in the Control Room area.
CLOSED 05-006-03 Establish a fire protection system Status Board for the Fire Protection Group Leader to assess operability.
O APPENDIX 9 I
I
I I I .
i-23-Oct-87 WC 86-41 SECTION 7.A.3 CLOSED 05-006-04 Assess program effectiveness in a formalized monthly report for upper management.
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O- APPENDIX 9
i
+
23-Oct-87
\- NRC 86-41 SECTION 7.B.1 Identification of Fire Barriers & Resolution of Penetration Discrep..
i i
DUE/ STATUS ACTION' .
1 y CLOSED 05-004-01 ~
j l Perform fire barriers walkdown'to identify l l barriers and penetrations. j i
'16-NOV-87. 05-004-02 p, Establish tracking mechanisms for tracking of new penetrations and for procedure revision.
l 1
CLOSED 05-004-03 d Prepare specifications.for procurement of equipment and material for existing penetration-
. seals.
l . t( f CLOSED 05-004-04 Resolve.(internally)'which fire barriers are .
required by Appendix R, Appendix A and Licensing 1 Commitments. Prepara drawings identifying boundaries to be maintained.
20-NOV-87 05-004-05 !
submit Appendix R Licensing clarification if needed. !
23-NOV-87 05-004-06 l Upgrade non-Appendix R barriers as required. l 23-NOV-87 05-007-01 Repair degraded seals and install new seals where l required in Appendix R Barriers. l e
1!
APPENDIX 9 i
i
-l, s 23-Oct-87 NRC 86-41 SECTION 8.A.1 j Weakness'in Responding to-QATFindings l
- DUE/ STATUS- ACTION CLOSED 08-001-04 Revise.the BEQAM'to include requirement for !
Vice-President notification 15 days before expiration of 90-day corrective action limit. ,
1 CLOSED 08-001-05 i Revise BEQAM to include requirement that
~~ unresolved Corrective Action issues are, automatically elevated to top management. . !
COMPLETED 08-001-06 Establish requirement that Vice-Presidents issue written reprimands to department managers who fail -i to meet deficiency report commitments.
\ CLOSED 08-001-07 Revise Nuclear Organization Procedure (NOP) to incorporate BEQAM Corrective Action requirements.
CLOSED 08-001-08 Train nuclear organization personnel on the Corrective Action Program and associated NOP.
CLOSED 08-001-09 Revise QA department deficiency report procedure to conform to the BEQAM for the handling of second responses to deficiency reports.
CLOSED 08-001-10 Revise the QAD Deficiency Report procedure description to better define the term "significant".
O APPENDIX 9 1
i NRC'86-41 SECTION 8.A.1 i
CLOSED 08-001-11 Assess organizational and corrective action program effectiveness by using key' performance indicators and periodic QAD reports.
1 Odm mw LO 9
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O APPENDIX 9 l
23-Oct-87
-( NRC 86-41 SECTION 9.A.1 j l
I l
Housekeeping Control DUE/ STATUS ACTION CLOSED 03-901-11 Establish and fill five exempt (supervisory) f positions in Station Services Group.
1 CLOSED 03-901-12 ,
Fill the position of Assistant Station Services Group Leader.
COMPLETED 03-901-13 Establish and fill thirty additional non-exempt positions in Station Services.
~
COMPLETED 03-901-14 ,
s Fill the ten Nuclear Plant Attendant positions in Station Services. !
l COMPLETED 03-901-15 Hire twenty utility workers in Station Services.
CLOSED 03-901-16 Maintain decontamination and housekeeping services at level of approximately 45 decontamination technicians.
COMPLETED 03-904-01 Issue housekeeping, radioactive material control and contamination control policy.
COMPLETED 03-904-02 Issue nuclear housekeeping procedure.
l COMPLETED 03-904-03 Assign area owners for housekeeping.
-l O- APPENDIX 9 i
l l
1
~
.23-Oct-87
'NRC 86-41 SECTION 9.A.1 CLOSED- 03-904-04 Establish area owners training course in housekeeping policy and in deficiency _ _
identification techniques.- Conduct training for !
. area owners initially. assigned. Course to be repeated as new owners are identified.
CLOSED 03-904-05 ~
Conduct frequent station tours by senior executive management-to increase the awareness-and demonstrate the importance of station cleanliness.
COMPLETED 03-904-06 Use nuclear organization morning meeting As a forum for addressing management issues concerning_
housekeeping deficiencies, areas of concern, and the decontamination plan for the day.
O 1
4 I
O. APPENDIX 9 1
a .
23-Oct-87
- 1,'
NRC 86-41'SECTION 9.B.1 Resolution of IS;I NDE Indications.on Safety Related Piping.
DUE/ STATUS ACTION !
i CLOSED 04-004-01 .
Continue required ISI. surface examination of ;
safety'related piping and identify unacceptable- 1 results in the NCR process. l 09-NOV-87 04-004-02 Perform ISI;of-pipe supports including expanding.
r- the sample of' supports to.be inspected when service induced problems.are'found. Identify l
. unacceptable conditions found and verify completion of corrective actions;under'NCRs..
CLOSED 04-004-03 Perform an overall' assessment of the RFO-6.and O RFO-7 ISI program results for root cause.
1
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i C, APPENDIX 9 1
I l
w i
1~ . 23-Oct-87 NRC 86-41'SECTION 10.A.1
-Technical' specification changes'to support Plant Startup DUE/ STATUS' ACTION- )
! .l 20-NOV-87 09-001-02 .I Establish'a list of criteria for Technical I specification changes which will include clarity J
, of basis, action statement /LCO agreement, precise: j wording. R CLOSED 09-001-03 . .<
' 5'- Schedule Technical specification review and '{
upgrade for.those Tech spec amendments required s before startup.
20-NOV-87 09-001-04 .I Develop schedule for streamlining Technical jrs specification review process. .
s- i 20-NOV-87 09-001-05 Establish a schedule of post-startup Technical Specification changes prior to startup from RFO-7. j l
CLOSED 09-001-06 Submit Technical Specification change request to ,
eliminate testing of redundant ECCS equipment. i t
i; l,
'l i
-O APPENDIX 9 i
l
APPENDIX 10 EXECUTIVE
SUMMARY
. A _ numerical . summary 'of. the status of a c t i o n ., i t e m s related to
~
known regulatory commitments follows: ;
-o Total items in Appendix 10:.................. 450 o . Total' items designated required for restart:. 424
~o Total items " COMPLETED":..................... 81-o Total items " CLOSED":........................ 235 I NOTE:: ' Appendix. 10 -is comprised of actions undertaken .to' address known regulatory commitments.- Appendices'8 and 9 are not separate lists of actions, but are sub-sets of items which are contained.in Appendix 10. They are ,
,- grouped in separate appendices for ease of review by I those concerned . primarily with actions related'to' CAL -
NO 86-10 and Management Meeting 86-41. -
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1i O
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i.
i APPENDIX 10 l i
RESTART REGULATORY COMMITMENTS !
Appendix 10 constitutes a consolidation of restart commitments from known sources. The principal' source of 1the commitment ~ is -
listed after each action item,.although some action items may r satisfy commitments made in more than one' source ~ document.
Notations in the'"DUE/ STATUS" are used as follows:
r~ -
(DATE) - Means that work on the item is.not finished.and '
the date indicates when- -i the action is expected to be complete and ready'for senior. management review.
50 -
conettrzo xee#- taet tae coeaize=e manager- considers the j
results achieved satisfy the action requirements, but that senior management is conducting a review'before' approving final closure of the item.- 1 CLOSED Means that senior !
management review has been completed, the 1 actions have received ;
i final approval and the
- documentation has been l retained in an item closure file.
4 O
4
Some actions are necessarily keyed to milestones and cannot be
[]
' assigned a specific date, but are dependent upon the sequence of j events surrounding that milestone. The status of such actions are indicated by the following. conventions:
RESTART Means that the action is part of or directly-tied to the actual reactor startup evolution or power ascension program. -
RFO 8 Means that the action is scheduled as part of
.the work to be done while the plant io shut ,
down for the next refueling outage. l.
(RS + ) Means that the action is scheduled for the Restart milestone plus some period of time which will always be . expressed in days. l EXAMPLE: RS+120 means that the action is !
scheduled to be completed 120 days after the !
r- reactor has been started up. This convention !
may be used with the other milestones in a similar manner. EXAMPLES: RFO 8-60 means-that the action is to bc. completed sixty days j before the scheduled beginning of refueling outage number eight. ILRT+90 means that the item is scheduled for completion ninety days after completion of the integrated leak rate O te t-i I
2 i .
l I 23-Oct-87 l
) '
OPERATIONS l .
1 ISSUE: 01-001 ;
OPERATIONS SECTION STAFFING l
DUE/ STATUS ACTION l CLOSED 01-001-01 I Hire Operations Section Manager.
(SOURCE: NRC MM 86-41) l CLOSED- 01-001-02 Hire Chief Chemical Engineer. !
(SOURCE: NRC MM 86-22)
CLOSED' ~~
01-001-03
' $ ~~ Assign two operations / Engineers to the Chief Operating Engineer as technical staf,f assistants.
(SOURCE: NRC MM 86-41)
CLOSED 01-001-04 Assign full time Planner to Operations gs section.
( (SOURCE: NRC MM 86-41)
CLOSED 01-001-05 Transfer Shift Technical Advisor function to operations.
(SOURCE: NRC MM 86-41)
CLOSED 01-001-06 Fill six'STA positions.
(SOURCE: NRC MM 86-41)
CLOSED 01-001-07 l Increase authorized complement of operators (total of equipment and reactor operators ) to 45.
(SOURCE: NRC MM 86-41)
RESTART 01-001-08 Man 4 shifts with one additional senior Reactor Operator (SRO) assigned to each shift for startup.
(SOURCE: NRC MM 86-30) i n 1 s
APPENDIX 10
p; 23-Oct-87 G OPERATIONS l
i 31-DEC->8 7 01-001-09 Recruit and train licensed reactor operators to support'a six section watchbill by'the and of 1987.
(SOURCE: NRC MM 86-41)
CLOSED 01-001-10 Assign an experienced Watch Engineer to assist training. 1 (SOURCE: NRC MM 86-41) i D
O APPENDIX 10
23-Oct-87 O
OPERATIONS 1
ISSUE: 01-002 CONTROL OF UORKER. OVERTIME DUE/ STATUS ACTION CLOSED 01-002-01 Establish an overtime policy for all personnel.
Require that department manager's approval of work ex'ceeding 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> / week.
(SOURCE: NRC MM 86-41)
CLOSED 01-002-02 Establish operation of a real-time, computer-based monitor to improve control of T --
operator overtime (including seven-day rolling average).
(SOURCE: NRC MM B6-41)
O I
i APPENDIX 10
4 23-Oct-87 .l
~\ OPERATIONS
- ISSUE: 01-063-VALVE'AND COMPONENT LABELING i DUE/ STATUS ACTION dLOSED 01-003-01 complete labeling of station valves. 1
'(SOURCE: BECO LTR 86.091) l u !
l
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O AreEnorx 10 l
1 l'
l 23-Oct-87 l
'O. OPERATIONS 1
ISSUE: 01-004 j OPERATIONS PROCEDURES IMPROVEMENTS j DUE/ STATUS ACTION-01-NOV-87 01-004-01 Revise Emergency Operating Procedures to;
-incorporate Rev.-4 of the BWROG Technical Guidelines. a (SOURCE: NRC,MM 86-32) -
CLOSED 01-004-02 l Proceduralize requirements-to log.RHR high
. pressure alarms.
v-- NRC EXIT 86-07)4 (SOURCE:
01-NOV-87 01-004-03 i Identify which instrument reat and isolation l valves need to be controlled. Establish how
- these valves will be controlled.
(SOURCE: - BECO LTR 86.091)
() CLOSED 01-004-04 Revise procedure 2.4.143 " Shutdown From Outside ,!
i Control Room" to include additional considerations addressed in NRC IR 85-30.
(SOURCE: NRC IR 87-22) 26-OCT-87 01-004-05 Correct the errors identified in procedure 5.3.21, " Bypassing of selected interlocks and isolation signals and inhibit-of Auto ADS".
(SOURCE: NRC IR 85-30)
CLOSED 01-004-06 Revised procedures to include APRM functional and setdown tests.
(SOURCE: NRC IR 86-07)
CLOSED 01-004-07 Develop procedures for use of breakers B310 and ;
B410 including how these buses should be transferred.
(SOURCE: NRC IR 84-26-01) l i.
N APPENDIX 10
w r
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. 1 23-Oct-87 4
i4 ' '( ' y OPERATIONS i
iI 4
\ 4 CLOSED 01-004-08,,1 n f R6solvethe[differenceinvalvepositions L ke between operating procedure 2.2.20 and drawings M242 and FSAR drawing Figure 7.4.8. .,. , 4 (SOURCE: NRC IR 87h*/1)
}
' . g' s 30-OCT-87 / 01-004-09 ;
Revise procedures to establish proper posithons )
of the RERS isolation injection >MO 1001-29A,an,d
'B:and MO 1001 28A'and B valves. (Procedure'} /,
nutaber!s 2.2.19, 2 . 2 . 8 6, .' 2 J'2 .'i t 5, , 8 .11. 2 . 2 , (
6.5.2.3, 8.5.2.6 and 8.7.1.411).
, (SOURCE:,1 / CAL 86-10) q
>s' ;'
(o CLOSED ' 01-004-10 ns I Ji I
JZ r- Revise alarm response prdeddur's 2.3.2.1 on panel C903-lef t annuncd ator B-7 RHR high '
pressure alarm.' s,;f ' ' '
n' y,
' (SOURCE: CAL 86-10)
/
30-OCT-87 01-004-l'1,\ ( o Revise RIIR sysflem surveillance procedure to i~ include'resultsand venting locati.ons.
O .<
~'tsg'unct: c^t 89-1o)
.< g .
30-OCT-87 01-004-12 Develop RHR system venting program. . Include, s adequate vent location for local high points and a method to control venting frequency by 4
. venting results. Y (SOURCE: CAL 86-10) /1 1
1 qj 5;i
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l APPENDIX 10 E
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t . . - - _ . _ _ . _ _ _ _ . _ _ _ _ _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
3 f f.
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6:
. , - . I.' 23-Oct-87
- r. 'd
( 4
, 3
, OPERATIONS i
.p. !
l ISSUE: ,
01-005-
., ,. IMPROVE ATTENTION TO DETAIL IN REGULATORY n' 8 MATTERS i b -
.RVf:/6TATUS' ,
! ACTION ]
1 I'
~30-OCT-8 :
01-005-01 Tf ; d.).- '
.f Review each recent NRC violation involving lack
? s. of attention to detail and analyze for common fl/'\) .g . cause. ' Develop corrective action. Plans.
o (SOURCE: .SALP 86-99)
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. ;p erg';;_c-c 4 . . .> . '
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,,. , >y s. O ?:7 <
, s c ., ,.
ISSUE:
)01-006 7: '; ' < , . ,;
/* IMPROVE ATTENTION TO DETAIL IN WATCHSTANDING. '-
q //
~
DUE/ STATUS ACTION il-OCT-87 01-006-01 -
. Retrain e_11. Control Room. personnel on the '! '
i importance of attention to detail in the
) performance of theiriduties and '
responsib11 ties. . 6 tress the importance of r i ,,
proper log'. keeping pr,actices and fo11ows3p with 1 watch supervisors and the tec,hnical branch on 5 all proble-i indications. , .A
, '(SOURCE: SALP 86-99) j
~
' 3 0-OCT N?, ','
01-006-02 s
' ' a
'i Retrain all control Room Person'nel on the i
/'
V importance.of being knowledgeable of'the status ,
of all plant equipment affecting operation,of I
(' the p3 ant including non-safety re'ated 4 equipment in the control Room. q SALP 86-99)
(SOURCE:
l
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l l
1 1
1 i
} g, h APPENDIX 10 '
1 4 J
i 23-Oct-87 OPERATIONS ISSUE: 01-007. 1 IMPROVE LOG' REVIEWS AND POST TRIP REVIEWS DUE/STATU,3 ACTION 15-NOV-87 .01-007-01 Retrain'tachnical staff personnel to conduct- .
thorough post trip-reviews to determine root cause, insuring that all such reviews are documented and that appropriate followup action is initiated. ;
SALP 86-99)
(SOURCE:
.i i
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i l
l APPENDIX 10 i I
i
- - - - - - - - - - - - - - - - - - - - - - _a
i 1
J 23-Oct-87
- v. j% b ss OPERATIONS ISSUE: 01-008 IMPROVE WATCHSTANDER CONTROL OF.HIGH RADIATION AREA ACCESS l
DUE/ STATUS ACTION 15-NOV-87 '01-008-01
. Train all personnel who. handle High Radiation Area keys on the importance of' maintaining !
control of keys to high radiation areas while insuring that controlled access for maintenance and surveillance inspections is allowed when appropriate without unnecessary delays.
(SOURCE: SALP 86-99) l
. i t
I APPENDIX 10 l 1
)
l
~1 l
es 23-Oct ~'
RADIOLOGICAL ISSUE: 02-001 RADIATION PROTECTION ORGANIZATION AND STAFFING IMPROVEMENTS )
DUE/ STATUS ACTION RS + 180 02-001-01 Develop a Radwasta Group.
(SOURCE: NRC IR 86-19-02) .
i 30-NOV-87 02-001-02 l Develop and document functional responsibility descriptions for all Radiological Protection supervisors.
s- --
(SOURCE: NRC IR 86-19-02) j CLOSED 02-001-03 Assign Health Physics Coordinators to the maintenance section for groups which have work loads which require substantial numbers of' Radiological Work Permits.
f-) (SOURCE: NRC MM 86-41)
\/ i i
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t
[")
'-' APPENDIX 10 l l
23-Oct RADI0 LOGICAL ISSUE: 02-002 PERSONNEL QUALIFICATIONS AND TRAINING IMPROVEMENTS DUE/ STATUS ACTION ;
CLOSED 02-002-01 ,
Relocate posting board at main control point'to !
a more conspicuous location.' .I (SOURCE: NRC IR 86-19-03) i 30-OCT-87 02-002-02 Revise the Training Manual to-incorporate v- _ qualification requirements for Radiological Protection personnel which are in agreement with the current job descriptions. -
(SOURCE: NRC IR 86-19-03) 30-OCT-87 02-002-03 -
Revise the Training Manual to resolve the discrepancies between the qualification- ,
( ). requirements for Radiological Protection l personnel and the requirements of ANSI 18.1.
(SOURCE: NRC IR 86-19-03)'
i i
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O-APPENDIX 10 1
I I
23-Oct-87 RADIOLOGICAL L ISSUE: 02-003 IMPROVE THE RELATIONSHIP AND COMMUNICATIONS BETWEEN RADIOLOGICAL PROTECTION SECTION AND OTHER STATION SECTIONS 1
DUE/ STATUS ACTION- l CLOSED 02-003-01 ;
Assign' radiological goals for each station !
section including tracking requirements and performance parameters. ,
(SOURCE: SALP 86-99)
CLOSED 02-003-02 Recognize individual achievement by an ALARA Employee of the Month award. j (SOURCE: SALP 86-99) i CLOSED 02-003-03 Include discussions of radiological protection groups interaction with other plant sections in
'the nuclear organizations daily and weekly
/~' meeting.
(SOURCE: SALP 86-99) 30-OCT-87 02-003-04 Section Managers include in plant tours observations of communications between the Radiological Protection Section and other station sections.
(SOURCE: NRC MM 86-41) i
( APPENDIX 10
l' Oct-87 RADIOLOGICAL
-ISSUE: 02-004 DECONTAMINATION i' DUE/ STATUS ACTION ,
-1
. RESTART- 102-004-01 Decontaminate areas in the Reactor Building !
quadrant rooms with safety related equipment so that these rooms can be toured without protective clothing.
(SOURCE: NRC MM 86-30) j i
CLOSED- 02-004-02 l Hydroblast floor drains to reduce exposure by 5 --
151 Manrem and hydroblart CRD headers to reduce exposure by 60 Manrem.
f (SOURCE: .NRC MM B6-41)
{
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\/ APPENDIX 10
H ')
4 i-l
' 23-Oct-87 I
-([)- RADIOLOGICAL H
j l
1 ISSUE: 02-005- 1 EP COUNTING LABORATORY' EQUIPMENT AND IMPROVE PRACTICES DUE/ STATUS ACTION l
CLOSED 02-005-01 .
I Conduct supervisor reviews of counting ,
laboratory data, particularly QA daily data. ]
(SOURCE: NRC IR 86-19-12) H 1
CLOSED 02-005-02 ')
Evaluate need for additional counting room I equipment. l
's -- ~
(SOURCE: NRC.IR 86-19-12)
CLOSED. 02-005-03 l Develop technical documentation or incorporate I into procedures the technical basis for QC 1 chart limits and LLD & MDA calculations. l (SOURCE: NRC IR 86-19-12) 1
() f 1
i i
4 I
i APPENDIX 10
- _ _ . _ . _ _ _ . _ . _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ w
l 23-Oct-87L
[^)
4 RADIOLOGICAL- )
1
~
ISSUE:- 02-006 IMPROVE RADIOLOGICAL PROTECTION PROCEDURES' 1
DUE/ STATUS- ACTION l CLOSED 02-006-01 Revise procedures for Alpha, counting of, smears e and similar procedures to include self-absorption factor.
(SOURCE: NRC IR 86-19) .
30-OCT-87 02-006-02 Ensure that procedureE6.9-197 includes all necessary reviews required by Generic Letter i-81-38.
(SOURCE: 'NRC IR 86-19) l 1
30-OCT-87 02-006-03 Revise the Contaminated Material Control procedure to establish curie-limits for
. temporary and permanent radioactive material j storage areas. '
(-)s (SOURCE: NRC IR 86-19)'
31-DEC-87' 02-006-04 Develop and implement a procedure for 1 decontamination, storage and issue of contaminated tools. '
(SOURCE: NRC IR 86-19) l CLOSED 02-006-05 Revise procedure 6.2-161 to incorporate !
appropriate guide and standards into procedural J reference for in-vitro monitoring.
(SOURCE: NRC IR 86-19) 1 CLOSED 02-006-06 Revise In-Vitro procedure to include specific instructions on obtaining fecal samples and 1 appropriate analysis for beta emitters.
(SOURCE: NRC IR 86-19)
CLOSED 02-006-07 !
[ Revise Internal Exposure Monitoring procedure ,
to evaluate Whole Body Count results, 'j respiratory protection adequacy, air sample and '
i:
APPENDIX 10 i
I
I IJ j'l.
.c. 23-Oct .
1 RADIOLOGICAL contamination survey results to ensure no undetected uptakes have occurred.
(SOURCE: 'NRC IR 86-19) 1 I
1
~
O i
k l-O APPENDIX 10
4 3 1
, , o 23-Oct-87 RADIOLOGICAL ,
ISSUE: .02-007 IMPROVEMENTS IN THE ALARA PROGRAM !
DUE/ STATUS ACTION ,
.. CLOSED 02-007-01 Develop ALARA program procedures.- _
(SOURCE: NRC.MM 86-41)
CLOSED- 02-007-02 'I Establish radiation exposure goals'and track and report results. :
(SOURCE: NRC MM 86-41)
~
NLOSED 02-007-03 Revise annual performance evaluation form to include ALARA performance.
(SOURCE: NRC MM 86-41)
~'
-CLOSED 02-007-04 ;
Determine that the radiation exposure goals are !
effective.
1 .
(SOURCE: _NRC MM 86-41)
CLOSED 02-007-05 Implement a continuing program to identify !
better methods-(including the' purchase of'
, additional equipment) to minimize, control and remove contamination. {'
(SOURCE: NRC MM 86-41)
COMPLETED 02-007 "5 Monitor effectiveness of purchased devices by tracking the number of times such devices are used and its effectiveness in controlling the spread of contamination. Use this effectiveness monitoring to identify better methods, as needed.
(SOURCE: NRC MM 86-41)
COMPLETED 02-007-07 Establish Nuclear Operating Manager as chairman of ALARA committee.
(SOURCE: NRC MM 86-41)
O APPENDIX 10 9
s
l RADIOLOGICAL RESTART 02-007 )
Monitor effectiveness of the ALARA program by I closely tracking collective station exposure !
and by assessing the effectiveness of the ALARA l committee and its recommendations. l (SOURCE: NRC MM 86-41) .)
CLOSED 02-007'09 ,
Establish an ALARA Employee of the Month award j for achievements in exposure reduction. l (SOURCE: NRC MM 86-41)
COMPLETED 02-007-10 Complete training on ALARA program and fully !
implement the program.
(SOURCE: NRC MM 86-41) i f
I i
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I l
APPENDIX 10
l l
23-Oct-87 A RADIOLOGICAL o l 1
ISSUE:- 02-008 1 IMPROVEMENTS IN THE RADIOLOGICAL OCCURRENCE REPORT-(ROR) PROCEDURE
- 1 DUE/ STATUS ACTION CLOSED 02-008-01 Upgrade Radiological occurrence Report (ROR) ,
procedure to improve categorization of ROR's by:
severity level. '
. j L (SOURCE: NRC MM:86-41) ]
CLOSED 02-008-02 L Assign a full time ROR coordinator. l
,_ (SOURCE: NRC MM 86-41)
CLOSED 02-008-03 .
]
Assign where possible ROR's to Group Leader '
level or above.
(SOURCE: NRC MM 86-41) i CLOSED 02-008-04 l g] Establish a computerized ROR tracking system. j
\/ (SOURCE: NRC MM 86-41) l f
H Y
I f
() APPENDIX 10 i
i
__ ______-_-__-___ _ O
. 4
[-t i 23-Oct-87
' RADIOLOGICAL ISSUE: 02-009 IMPROVE THE RADIOLOGICAL PERFORMANCE OF PILGRIM STATION PERSONNEL i
DUE/ STATUS. ACTION CLOSED 02-009-01 Involve Line' Managers in routine reinforcement of' radiological requirements. .
i (SOURCE: NRC MM 86-41)
CLOSED 02-009-02 Reassign responsibility for implementing disciplinary action for radiation protection i
, - - violations from Radiological Section Manager to individual supervisors. .
(SOURCE: 'NRC MM 86-41)
CLOSED 02-009-03 Revise GET program to emphasize that the basis
.. for radiological protection isEto ensure the health and safety of individual workers.
().. (SOURCE: NRC MM 86-41)
CLOSED 02-009-04 Conduct formal training programs in contamination control. techniques for ,
operations, maintenance and radiological l supervisors, workers and technicians. I (SOURCE: NRC MM 86-41) i l
l APPENDIX 10
23-Oct-87
~ O RADIOLOGICAL ,
f ISSUE: .02-010 IMPROVEMENTS IN THE ENVIRONMENTAL TLD SYSTEM DVE/ STATUS ACTION CLOSED 02-010-01 Replace existing environmental.TLD system by Panasonic Environmental TLD System.
(SOURCE: NRC MM 86-41)
,- CLOSED 010-02 Implement procedures to send Panasonic Environmental TLDs to an independent laboratory
~
for irradiation on a quarterly basis. I s-- -
(SOURCE: NRC MM 86-41) {
CLOSED 02-010-03 Continue to participate in the International Environmental Dosimeter Intercomparison ,
Project.
(SOURCE: NRC MM i -41)
CLOSED 02-010-04 Develop a QA procedure for the new Environmental TLD System program.
(SOURCE: NRC MM 86-41)
CLOSED 02-010-05 Evaluate Environmental TLD program i effectiveness using TLD intercomparison l studies.
(SOURCE: NRC MM 86-41)
I l
!{,
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(2) APPENDIX 10 !
l 1
1
1 l
_3 23-Oct-87 RADIOLOGICAL i I
ISSUE: 02-012 DISPOSITION OF THE RADIOLOGICAL SECTION BACKLOG 1
DUE/ STATUS ACTION dLOSED 02-012-01 Identify and dispose of Radiological Section backlog to a manageable level.
(SOURCE: NRC MM 86-41) j 1
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I APPENDIX 10 l
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L_____--__--_____.
1 l
23-Oct-87
]
/ T~ I
(/ MAINTENANCE ISSUE: 03-901- 1 MAINTENANCE SECTION STAFFING DUE/ STATUS ACTION !
CLOSED 03-901-01 Fill existing supervisory vacancies. ;
(SOURCE: NRC MM 86-41) !
l COMPLETED 03-901-02 Computerize administration of overtime control.
(SOURCE: NRC MM 86-41)
CLOSED 03-901-03
'~ ~~
Establish and staff a Procurement Support Group I (PSG) to facilitate processing of procurement f documents. 1 (SOURCE: NRC MM 86-41)
CLOSED 03-901-04 Develop a centralized planning and scheduling.
function within the Maintenance Group to directly support the individual maintenance disciplines..
(SOURCE: NRC MM 86-41)
CLOSED 03-901-05 Hire three additional maintenance staff engineers.
(SOURCE: NRC MM 86-41) l l
CLOSED 03-901-06 Hire one HVAC supervisor.
(SOURCE: NRC MM 86-41)
CLOSED 03-901-07 Establish apprenticeship program in the three ,
maintenance disciplines with twelve apprentice '
positions approved. ;
NRC MM 86-41) l (SOURCE:
COMPLETED 03-901-08 Accelerate the process of filling open l Maintenance supervisory positions.
1 (SOURCE: NRC MM 86-41)
() APPENDIX 10
l \
V
- - - + :23-Oct-87 MAINTENANCE-a RS'+ 90 03-901-09 Evaluate long-term Maintenance Section' staffing ,
l4 plan.-
(SOURCE: NRC MM 86-41)
CLOSED 03-901-10 Establish management tours to1 assess the effectiveness of supervisors in enforcing high standards.
(SOURCE: NRC MM 86-41)
CLOSED 03-901-11 Establish and' fill five exempt (supervisory) positions in station services Group. . !
(SOURCE: NRC MM 86-41) l CLOSED 03-901-12 . i Fill the position of Assistant Station Services j Group Leader.. 1 (SOURCE: NRC MM.86-41)
COMPLETED 03-901-13 Establish and fill thirty additional non-exempt
' -( ). positions in station services.-
(SOURCE: NRC MM 86-41)
COMPLETED 03-901-14 i I
Fill the ten Nuclear Plant Attendant positions in Station services.
(SOURCE: NRC MM 86-41) !
COMPLETED '03-901-15 Hire twenty utility workers in Station :
Services. l (SOURCE: NRC MM 86-41)
-CLOSED 03-901-16 l Maintain decontamination and housekeeping j services at level of approximately 45 1 decontamination technicians. l (SOURCE: NRC MM 86-41) l l
CLOSED 03-901-17 l Improve the rate of reducing outstanding a maintenance backlog by increasing contractor .j work force (including engineers, supervisors ]
and craft). ll l
APPENDIX 10 l
h I
.,- 23-Oct-87 MAINTENANCE
=
(SOURCE: NRC MM 86-41).
' ~
CLOSED 03-901-18 8trengthen BEco oversight of maintenance contractors by ensuring First Line supervisors
. observe the work in the field under their-responsibility on a daily basis. ;
(SOURCE: SALP 86-99) !
COMPLETED 03-901-19 s.i . Replace the contractor personnel filling the positions of senior Mechanical Engineer and IEC ,
supervisor with permanent Boston Edison
-employees. t (SOURCE:- BECO LTR 87.130)
CLOSED ~03-901-20 .
}
Establish a Maintenance Apprentice Training' Program with sufficient input to produce an' i average graduating class of about two electricians, three nuclear control technicians and four mechanics. .i (SOURCE: BECO .LTR 87.130)
.O l-1 I
l l
APPENDIX 10 i
)
i
1 l
, 1 l
23-Oct'-87 MAINTENANCE l l
ISSUE: 03-902 CENTRALIZED CCMTROL OF MAINTENANCE PLANNING
'DUE/ STATUS ACTION CLOSED 03-902-01 Establish maintenance planning group with full time planners.
(SOURCE: NRC MM 86-30)
CLOSED 03-902-02 a Centralize maintenance planning and scheduling j activities. 1 (SOURCE: NRC MM 86-41)
CLOSED 03-902-03 l Develop weekly planning / scheduling e'ffort for routine maintenance activities. l (SOURCE: NRC MM 86-41) l CLOSED 03-902-04
()
/~% correct the data contained in the administrative control system for MRs.
(SOURCE: . NRC MM 86-41) e I
COMPLETED 03-902-05 )
Coordinate maintenance activities between the ;
various disciplines through. weekly planning and {
scheduling meeting. q (SOURCE: NRC MM 86-41) J
\
CLOSED 03-902-06 !
Implement new maintenance manual to provide j guidance for conduct of planning / scheduling I effort. l (SOURCE: NRC MM 86-41) l CLOSED 03-902-07 Restructure maintenance group to provide increased management attention to both outage-related maintenance and backlog.
(SOURCE: NRC MM 86-41)
RS + 60 03-902-08 l Prepare and issue the Long Term Plan (schedule) for accomplishing plant modifications. The LTP 1 L
APPENDIX 10
',j 23-Oct-87.
MAINTENANCE '
4
' is to clearly show those portions of'SEP mods !
and other design' changes which have been i deffered for accomplishment after RFO-7. .j (SOURCE: SALP 86-99)
/
9 4.= m-v j
l l
1 l
l l
l l
APPENDIX 10
l
- 23-Oct-87 I
~
MAINTENANCE !
ISSUE: 03-903 i COMMUNICATION BETWEEN MAINTENANCE AND OTHER SITE ORGANIZATIONS ,
DUE/ STATUS ACTION j i
CLOSED 03-903-01 !
Discuss maintenance interaction with other !
plant sections at nuclear organization morning i meeting and at weekly staff meetings.
(SOURCE: SALP 86-99)
CLOSED 03-903-02 i Establish a method to prioritize MRs and inform i 5-affected departments of results. i (SOURCE: NRC MM 86-41)
CLOSED 03-903-03 !
Establish a plan-of-the-day work prioritization !
which includes all disciplines related to the-approved schedule.
(SOURCE: NRC MM 86-41)
CLOSED 03-903-04 Attend industry conference on maintenance / operation interface.
(SOURCE: NRC MM 86-41)
CLOSED 03-903-05 Establish an MR feedback system to ensure that the cognizant organization is informed if the MR will not be worked as planned. 1 I
(SOURCE: NRC MM 86-41) 1 1
. i
'l i!
f!
([) APPENDIX 10 f
l 2
f
\
-- - - _ - _ __----____________J
i F
1
'i Oct-87
. (~1 i
-" MAINTENANCE i i
ISSUE: 03-904 HOUSEKEEPING CONTROL DUE/ STATUS ACTION j
)
COMPLETED 03-904-01 l Issue housekeeping, radioactive material-control and contamination control policy.
(SOURCE: NRC MM 86-41)
COMPLETED 03-904-02 Issue nuclear housekeeping procedure.
(SOURCE: NRC MM 86-41) 5 COMPLETED 03-904-03 ,
Assign area owners for housekeeping. ;
(SOURCE: NRC MM 86-41) j CLOSED 03-904-04 Establish area owners training course in housekeeping policy and in deficiency f- identification techniques. Conduct training
( ,f for area owners initially assigned. Course to be repeated as new owners are identified. 'q (SOURCE: NRC MM 86-41) l I
CLOSED 03-904-05 l Conduct frequent station tours by senior executive management to increase the awareness and demonstrate the importance of station cleanliness.
(SOURCE: NRC MM 86-41)
COMPLETED 03-904-06 Use nuclear organization morning meeting as a forum for addressing management issues concerning housekeeping deficiencies, areas of I concern, and the decontamination plan for the I day.
(SOURCE: NRC MM 86-41)
APPENDIX 10 l
1
4.
1 23-Oct -
' MAINTENANCE ISSUE: 03-905 PREVENTIVE MAINTENANCE PROGRAM IMPROVEMENTS DUE/ STATUS ACTION !
RESTART 03-905-01 Use performance indicators to determine the
. effectiveness of program improvements in the
-area of preventive maintenance.
(SOURCE: SALP 86-99)
CLOSED 03-905-02 Update preventive maintenance tracking list.
r (SOURCE: NRC MM 86-41)-
CLOSED 03-905-03 l Have maintenance planners schedule PM' j i
-activities and incorporate reviews and. update status. 4 (SOURCE:- NRC MM 86-41) !
l
, COMPLETED 03-905-04 b The Compliance Group shall issue variance reports on PM activities in accordance with the .s (SOURCE: NRC MM 86-41) 1 COMPLETED 03-905-05 Clarify procedural requirements and increase effectiveness of tracking list by revising PM tracking procedure; increase management attention by notifying responsible group leader l of failure to perform a PM. Elevate to Section i Manager attention upon third consecutive j non-performance. J (SOURCE: NRC MM 86-41)
CLOSED 03-905-06 Trend PM performance for each discipline in the maintenance group.
(SOURCE: NRC MM 86-41)
CLOSED 03-905-07 Develop and issue PM procedures for Limitorque motor operated valves.
(SOURCE: NRC MM 86-41)
O APPENDIX 10
__.---_--A
TJ ,
r^) 23-Oct-87 s
\_/-
MAINTENANCE 01-MAR-88 03-905-08 Evaluate the failure analysis reports of motor ,
operated valve failures to determine the .!
ndequacy of the failure analysis reports.
(SOURCE: NRC MM 86-41) dLOSED 03-905-09 Resolve the 125V and 250V DC battery preventive maintenance issues.
(SOURCE: NRC IR 87-09)
COMPLETED 03-905-10
' Provide the'NRC plans and schedules for initiating a baseline PM program for safety related'480 VAC molded case breakers.
~ ~~
(SOURCE: NRC IR 86-06)
CLOSED 03-905-11 Develop and issue PM requirements for Limitorque motor operated valves. ;
(SOURCE: NRC MM'86-41)
()
I j
1
.q l
1 O APPENDIX 10
e 1 ,
I 23-Oct-87 MAINTENANCE.
i i
. ISSUE: 03-906 MAINTENANCE. MONITORING AND TRENDING ;
DUE/ STATUS ACTION l.
Ol-NOV 03-906-01 The Station Manager vill utilize the key .. i indicators to measure maintenance performance.- t Goals will be established and progress tracked monthly. )
(SOURCE: SALP 86-99) .]
RESTART 03-906-02 Improve Maintenance Group performance trending j
-~
$ ~~ system and include ways to identify.and correct ]
areas of weakness. .
J (SOURCE: NRC MM 86-41) l COMPLETED 03-906-03 ,
Review FEMR trend analysis to determine whether MCARs would be applicable / appropriate to address root cause of cracked.. welds and loose
.O- bolts in low pressure ECCS systems. ]
(SOURCE: KRC MM 86-41) .
COMPLETED 03-906-04 Implement corrective action training for NED ']
personnel.
(SOURCE: NRC MM 86-41) l i
l l
APPENDIX 10
- 1 1
I
.r.. 1 1
'23-Oct-87
.N mf
-J MAINTENANCE-
~ ~
ISSUE: 03-908 , i GENERAL TESTING:IBSUE 1.
f R
~
I pyJ/ STATUS ACTION e dLOSED- 03-908-01 !
Perform back-up' scram valve testing each '
refueling outage.
.(SOURCE: .NRC IR 86-21). ;
CLOSED 03-908-02 !
Test PABS piping that was not repinced as a l result of'1984 investigation.for IGSCC.
(SOURCE:- NRC,IR 87-01) .
,- l RESTART 03-908-D3 i Complete hydro testing schedule per long term program integration. 3 (SOURCE: BECO LTR 2.86.148) . , ,
([) u i
\
l
.} }
1.,
l f
s- l H
! O- APPENDIX 10
, J t
y 23-Oct-87
~O' '
,1 MAINTENANCE l
ISSUE: 03-909 I E C:MSIV/ MODE SWITCH PROBLEMS / LOOSE WIRES AND FUSE IN SAFETY RELATED SYSTEMS DUE/S$~IUS -ACTION CLOSED 909 Install GETARs to monitor primary containment isolation system during comprehensive testing during next startup. .
(SOURCE: LER 86-010) j CLOSED 03-909-02 Reassemble, inspect and rebuild MSIVs.
i- (SOURCE: CAL 86-10) i CLOSED 03-909-04 !
l Replace Mode Switch with G.E. recommended model, f (SOURCE: CAL 86-10")
r ;
f CLOSED 03-909-05 i t close out the following MRs to. correct various !
,, circuit problems:~86-45-189, 8G-45-190, 86-45-191, 86-45-192, 86-45-193,86-300, 86-301,86-302.
~(SOURCE: CAL 86-10)
COMPLETED 03-909-06 i
,, Evalunto the loose neutral wiring of RPS/PCIS l syaten. l (SOURCE: NRC MM 86-41) f CLOSED 03-909-07 Identify prior similar termination problem events (similar to loose neutral wiring of l Action,Eumrcr 03-909-06).
l (SOURCE: NRC MM 86-41) c ,
COMPLETED 03-909-06 I
Analyze termination deficiency events and l recommend corrective' actions concerning loose wire problems.- !
(SOURCE: NRC MM 86-41) 4:
I z !
l '
6 .
i APPENDIX 10
. _ _ _ _ _ _ _ _ _ _ ____.________________ _ _ __3
4, L
"3.i i ' .l
[. ;, ,
/ .1, f) 23-Oct-87
,. -[t ~,
MAINTENANCE
$@g ". p n .
g'br #
RESTART 03-909-09 I i' Revise station procedures requiring removal of
[C 3 fuses in performance of tests;and.specify m6thod of checking fuse tightness.
i.
., (SOURCE: NRC MM 86-41)
. t.
'00MPLETED 03-909-10
.i Ynysstigate applicability of new incipient ,
failure detection techniques to provide early. (
j detection of loose wires and termination deficiencies.
,f (SOURCE: NRC.MM 86-41)
U COMPLETED 03-909-11
- Aseess the effectiveness of the correction of r- electrical connector tightness problems.
Monitor FEMR reports to determine trends.
(SOURCE: NRC MM 86-41)
/
(
1 l
i APPENDIX 10
L I I l
~'\ 23-Oct-87
~(J MAINTENANCE ISSUE: .03-910
- I&C IRM NEUTRON MONITOR PROBLEMS DUE/ STATUS ACTION CLOSED 03-910-01
- Evaluate SIL 445, INPO SER and GE RIC'SIL'0071 for application to PNPS 2RM designs.
(SOURCE: NRC MM 86-41)
RESTART 03-910-02 Functionally test IRMs.
(SOURCE: NRC MM 86-41)
'EESTART 03-910-03 Increase existing fuse capacity by 100%.
l (SOURCE: NRC MM<86-41)
CLOSED 03-010-04 Evaluate SIL 445 recommendation to add voltage i sensing relays. ;
.f]). (SOURCE: NRC MM 86-41) f I
AFPENDIX 10
t Oct-87
, MAINTENANCE ISSUE: ^
03-911 I & C. REACTOR WATER LEVEL AND TRIP SYSTEM DUE/ STATUS ACTION RESTART 03-911-01 .
Install an analog trip system'to reduce'the probability of inadvertent scrams during surveillance testing.
(SOURCE: LER 85-006).
COMPLETED 03-911-02 i Reroute reference legs in accordance with i l'~ ~~
BWROG/GE. recommended mod to eliminate
" flashing"-and resultant inaccurate water level indication.
(SOURCE: BECO LTR 85.099) i CLOSED 03-911-03 Review instrument setpoints to ensure initiation of related safety system trips under
[ abnormal drywell conditions. .
(SOURCE: BECO LTR 85.099)
CLOSED 03-911-04 Develop and issue a PDC to address the establishment of a common zero reference for reactor water level measurement.
(SOURCE: BECO LTR 82.046) i i
l i
1[)F APPENDIX 10 l
1 l
l l
23-Oct-87
..O MAINTENANCE
/
-ISSUE: 03-912 I E C LOGIC SYSTEM FUNCTIONAL TEST WEAKNESSES DUE/ STATUS. ACTION NESTART 03-912-01 l Resolve ECCS Logic System Functional Testing l adequacy.
(SOURCE: NRC IR 86-21)
functional tests. l (SOURCE: NRC IR 86-21) !
,_ _ q O
1 i
O APPENDIX 10
. c 23-Oct-87~
MAINTENANCE ISSUE: 03-913 ELECTRICAL USE OF FUSE 8;AND METAL LINKS ~IN
-CONTROL CIRCUITRY DUE/ STATUS ACTION RS:+ 270 03-913 1 Determine where. links-are used in safety related motor control circuits.
.(SOURCE: NRC MM 86-41)
CLOSED = 03-913-02 ~
Perform Engineering evaluation to replace metal links with fuses in Appendix R related motor control circuits..
'~
(SOURCE: NRC'MM 86-41)
RS + 270, 103-913-03 Correct drawings to reflect fuses / links' based on walkdown/ Engineering' evaluation.
(SOURCE: 'NRC MM 86-41)
- () RESTART 03-913-04 Implement' plant design changes (based on Engineering evaluation 86-41-3.B.16-2.1) th' replace Appendix R related metal links.
(SOURCE: NRC MM 86-41)
RS + 150 03-913-05 Perform engineering evaluation to replace metal links with fuses in non-safety related motor control circuits.
(SOURCE: NRC MM 86-41)
RS + 270 03-913-06 Implement plant design changes (based on .
Engineering evaluation 86-41-3.B.16-2.1) to replace non-safety related metal links.
(SOURCE: NRC MM 86-41) ,
H RS + 150 03-913-07 Review non-safety related motor control circuit drawings for metal links that require replacement with fuses.
(SOURCE: NRC MM 86-41) n U APPENDIX 10 i
I t
-f 23-Oct-87 1
( '
l MAINTENANCE l I
i ISSUE: 03-914 '!
MECHANICAL SECONDARY CONTAINMENT DAMPERS AND SEALS !
DUE/ STATUS ACTION RESTART 03-914-01 !
Identify and replace defective rubber boots I
that seal secondary containment penetrations for feedwater lines.
j (SOURCE: 'NRC IR 86-07)
CLOSED 03-914-02 Identify'and document root cause for secondary r- -
containment damper failures.
(SOURCE: NRC MM 86-41)
CLOSED 03-914-03 Develop list of secondary containment dampers
, affected by root cause.
(SOURCE: NRC MM 86-41)
(
COMPLETED 03-914-04 Replace secondary containment dampers.
(SOURCE: NRC MM 86-41)
I 1
I O APPENDIX 10 l
i
l H ,
f i
)
'23-Oct-87 )
,i).
is MAINTENANCE ISSUE: 03-915 MECKANICAL - HPCI TURBINE EKKAUST SYSTEM DEFICIENCIES DUE/ STATUS. ACTION CLOSED 03-915-01 Perform root cause analysis of HPCI turbine exhaust water hammer problem. '
(SOURCE: NRC MM 86-41)
RESTART 03-915-02 Implement EPCI exhaust line vacuum breaker upgrade.
i- (SOURCE: NRC MM 86-41) t RESTART 03-915-03 Conduct post. construction operability testing to verify HFCI turbine exhaust modification effectiveness.
(SOURCE: NRC MM 86-41) ,
70 i
O APPENDIX ?.0 I
1
l l
-q- 23-Oct-87
~ ~
MAINTENANCE ISSUE: 03-916 MECHANICAL - CRACKED WELDS & LOOSE BOLTS IN ECCB DUE/ STATUS ACTION RESTART 03-916-01 Replace the. sleeve at reactor vessel N-16A during RFO-7 because of cracked weld identified on reactor water level instrument line.
(SOURCE: LER 86-006-00)
CLOSED 03-916-02 Review previous action taken on failure s-- --
analysis for cracked welds and loose bolts in ECCS.
(SOURCE: NRC MM 86-41)
CLOSED- 03-916-03 Investigate root cause of weld failures.
(SOURCE: NRC MM 86-41) l CLOSED 03-916-04 l Perform root cause evaluation for bolt failures.
(SOURCE: NRC MM 86-41)
COMPLETED 03-916-05 Install replacement yokes.
(SOURCE: NRC MM 86-41)
RFO-8 03-916-06 Implement corrective actions to address root causes of weld failures identified in Action Number 03-916-03. l (SOURCE: NRC MM 86-41) ]
I l
l 1
I 3
APPENDIX 10
y
)
- rw - 23-Oct-87 i .
MAINTENANCE ISSUE: 03-917 MECHANICAL RHR & CORE SPRAY PROBLEMS.
DUE/ STATUS ACTION CLOSED 03-917-01 Install additional pressure gauges in RER.
system per PDC 86-30.
(SOURCE: CAL 86-10) 30-OCT-87 03-917-02 Provide means for system temperature monitoring.
(SOURCE: CAL 86-10)
.s COMPLETED 03-917-03 Remove; pressure gauge installed on RER injection line to allow for a vent path.
(SOURCE: CAL 86-10) '
-CLOSED 03-917-04
'"s Remove valve disk and evaluate or. restore to (v) confirm the wear rate.
(SOURCE: CAL 86-10) 10-NOV-87 03-917-05 Local venting in RHR to be performed once a week for four weeks per TP 86-84.
(SOURCE: CAL 86-10) 31-OCT-87 03-917-06 Retest the boundary valves of the RHR vessel injection'line for Appendix J criteria and for high pressure water leakage. Conduct engineering evaluation of results.
(SOURCE: CAL 86-10)
CLOSED 03-917-07 Replace RHR injection gate valve 29B, per PDC 85-75.
(SOURCE: NRC MM 86-22)
COMPLETED 03-917-08 Disassemble and inspect RER B loop valve ;
1001-36B next refuel outage. '
(SOURCE: NRC IR 86-07)
(~ ,
A-) APPENDIX 10 l
l
t i 1
i 23-Oct-87 MAINTENANCE LCOMPLETED. 03-917-09 Disassemble, inspect and conduct preventive maintenance program on RHT, pumps.
(SOURCE: NRC MM.86-41)
CLOSED' 03-917-10 Replace RER pump-impeller wear rings.
(SOURCE: NRC MM 86-41) l CLOSED 03-917-11 .i visually inspect RHR pump wear rings for cracking.
(SOURCE: NRC MM 86-41) 1 CLOSED- 03-917-12 T- Conduct metallurgical evaluation ofLRHR pump impeller wear rings.
(SOURCE: NRC MM 86-41)
CLOSED 03-917-13 Transmit results of RHR and core spray pump inspection to NRC.
(SOURCE: NRC MM 86-41)
- CLOSED 03-917-14 1 Disassemble, inspect and rebuild core spray ,
pumps. l (SOURCE: NRC MM 86-41)
RFO-8 03-917-15 ,
schedule accomplishment of resultant design- {
modifications on check valve position indicatorn, via the long term program.
(SOURCE: CAL 86-10) 31-MAR-88 03-917-16 I After trial use as a temporary procedure evaluate and change as required TP 86-85 and l incorporate it as a part of the RHR system operating procedure.
(SOURCE: CAL 86-10)
RFO-8 03-917-17 I Evaluate RHR injection gate valve 29A for replacement.
(SOURCE: NRC MM 86-22) l
- C]f APPENDIX 10 l
i j
I
I
,f s 23-Oct-87
%u)
MAINTENANCE
~
ISSUE: 03-918 MECHANICAL RHR/DRYWELL. SPRAY CROSS-CONNECT pt!E/ STATUS ACTION RESTART 03-918-01 Fire water system will be interconnected to RHR system to provide additional source of water for drywell spray (installation).
'(SOURCE: NRC MM 86-32)
CLOSED OJ-918-02 Fire water system will be interconnected to RHR system to provide additional source of water i
for drywell spray (design).
(SOURCE: NRC MM 86-32) l
+0, V
l O APPENDIX 10
. . gs 23-Oct-87 U MAINTENANCE' 1
ISSUE: 03-919 MECHANICAL MINIMUM FLOW PROTECTION FOR RHR PUMPS-DUE/ STATUS ACTION CLOSED 03-919-01 i Revise safety evaluation for existing l PDC 86-95 ,
to establish minimum flow design basis, revise PDC 86-95 accordingly.
(SOURCE: NRC MM 86-41)
COMPLETED 03-919-02 g Correctly install orifice plate in RHR minflow i x line.
(SOURCE: NRC MM 86-41)
CLOSED 03-919-03 ,
Review RHR minflow operating logic and issue appropriate design changes.
(SOURCE: NRC MM 86-41)
( RESTART 03-919-04 Install PDC 86-33 (MO 1001-18 AEB).
(SOURCE: NRC MM 86-41)
RESTART 03-919-05 Install PDC 86-95 to establish minimum RHR flow.
(SOURCE: NRC MM 86-41) l i
APPENDIX 10
p
't 23-Oct-87
' ('\ '
MAINTENANCE
. ISSUE:
03-920 MECHANICAL CORE SPRAY-CHECK VALVE E'MOV PROBLEMS
]
DUE/ STATUS ACTION CLOSED' 03-920-01 l i
. Evaluate scope:and root cause of problem of 1 core spray.. test check valve internal disc becoming disassociated from the swing lever i arm.
(SOURCE: NRC MM 86-41) ,
COMPLETED 03-920-02
,. Confirm no similar vertical installation.
(SOURCE: 'l NRC MM 86-41)_
CLOSED 03-920-03 Install new discs including anti-rotation pins in disc of susceptible check valves temporarily until new discs with anti-rotation stops and improved materials are installed.
.{) (SOURCE: NRC MM 86-41)
RESTART 03-920-04 Verify continuing valve operability (CV1400-35 ;
and 214) through routine system surveillance. '
(SOURCE: NRC MM 86-41)
CLOSED 03-920-05 Prepara or revise procedure to ensure that correct MOV (Limitorque) switch settingts are i determined and maintained for the life of the l plant. l (SOURCE: BECO LTR 86.059) l l
RESTART 03-920-06 Correct the MOV (Limitorque) switch settings.
(SOURCE: BECO LTR 86.059)
RESTART 03-920-07 Stroke test each identified MOV (Limitorque) requiring switch setting re-adjustment to verify the switch settings. l (SOURCE: BECO LTR 85.059) l
( APPENDIX 10 L______.__.m__-__ _ _ _ . <>
23'-Oct-87
[v~i' MAINTENANCE OCT-87 03-920-08 Review motor-operated valves for inconsistent sizing and oversizing of motor overload devices.' )
(SOURCE: NRC MM 86-41) ]
RFO-8 03-920-09 If necessary, implement the physical change I and/or configuration necessary.to resolve check- I valves. designed for vertical service or j reconfigure existing check valves for i horizontal use. J (SOURCE: NRC MM 86-41) j 1
c-
}
i 1
()
)
)
O APPENDIX 10 l
s 23-Oct-87 MAINTENANCE
~
1SSUE: 03-921 MECHANICAL PASS PIPING PROBLEMS DUE/ STATUS ACTION.
COMPLETED 03-921-01 Perform an engineering evaluation to determine the current condition of the PASS piping due to chloride contamination and an assessment of the suitability of the pipe for continued. service.
(SOURCE: NRC IR 87-01) i O
i l
APPENDIX 10 l
l
r
'\'
)
/~N 23-Oct-87 U
MAINTENANCE J '
1 L
ISSUE: 03-922 j MECKANICAL RESIDUAL RCIC FLOW INDICATION AFTER '
SURVEILL;LNCE DUE/ STATUS ACTION RESTART 03-922-01 Investigate the cause and required corrective actions for the residual RCIC flow indication occasionally noted after RCIC surveillance tests.
(SOURCE: NRC IR 86-06) y_
V 4
.A kl APPENDIX 10
)
23-Oct-87
/-s\ .
MAINTENANCE ISSUE: 03-923 l DRYWELL SPRAY AND CONTAINMENT VENTING j DUE/ STATUS ACTION RESTART 03-923-01 Complete modifications addressing drywell spray l capability. l (SOURCE: NRC MM 86-32) {
ON HOLD 03-923-02
' Complete modifications addressing containment venting capability. (Containment Venting on !
hold - see NRC letter dated 8/21/87 Docket No.. f s- 50-293). j (SOURCE: NRC MM 86-32) ;
i C:)
APPENDIX 10
_1________:-- -
k
.s 23-Oct-87 ,
- -! MAINTENANCE ISSUE: 03-924 SALT SERVICE WATER PIPING CORROSION 1 DUE/ STATUS ACTION CLOSED 03-924-01 l Establish scope of problem.
(SOURCE: NRC MM 86-41)
CLOSED .03-924-02 Perform root cause study of SSW corrosion.in screenhouse and buried piping.
(SOURCE: NRC MM 86-41) sRESTART 03-924-03 Replace salt witer components as necessary per- ;
PDC 86-22. Install test material piping piece. 1 in screen wash piping.
(SOURCE: NRC MM 86-41) j COMPLETED- 03-924-04 Investigate integrity of salt water pumps.
.( ). (SOURCE: NRC MM 86-41)
COMPLETED 03-924-05 Investigate integrity of salt water pipe including screen wash piping.
(SOURCE: NRC MM 86-41)
RFO 60 03-924-06 I Provide inspection. criteria for routine f inspections, 2 months before RFO-8. J (SOURCE: NRC MM 86-41)
CLOSED 03-924-07 Issue design change modification to replace / repair degraded components.
(SOURCE: NRC MM 86-41)
RFO-8 -180 03-924-08 Identify improved materials for SSW service 6 months before RFO-8.
(SOURCE: NRC MM 86-41)
I APPENDIX 10 o :
l-
k i
IT A/
23-Oct-87 i MAINTENANCE 20-NOV-87 03-924-09 .
Investigate cause of incorrect status report i for 88W piping and implement corrective action. !
'(SOURCE: BECO LTR'87.070)
CLOSED 924-10 Repair / replace degraded components.
- fSOURCE: NRC MM 86-41) .}
's ' -
f' 1
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O APPENDIX 10 L1_---___ _- - --_ - -- - - . _
j
1 I
1 1
,_ 23-Oct-87 MAINTENANCE l
i ISSUE: 03-925 ]
POTENTIAL CORROSION OF PRIMARY CONTAINMENT j ISOLATION-VALVES DUE/ STATUS ACTION CLOSED 03-925-01 Develop. list'of Clow corporation butterfly '
valves (wafer type) that are used at PNPS. l (SOURCE: NRC MM 86-41)
COMPLETED 03-925-02 Examine one of the eight Clow valves and review results with the valve vendor, and respond to r ESR 87-590.
(SOURCE: NRC MM 86-41)
RESTART 03-925-03 continue normal monitoring of valve operation during LLRT and valve timing tests. l (SOURCE: NRC MM 86-41) :
j O -
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4 l
F o
(' i APPENDIX 10 1
f 23-Oct-87 O MAINTENANCE ISSUE: 03-926 <
BBGT DESIGN MODIFICATION l
DUE/ STATUS ACTION COMPLETED 03-926-01 Correct SBGT deluge system to preclude inadvertent actuation. Modify SBGT to eliminate remaining design deficiencies and single active failures, including SBGT heatars monitoring for failure.
(SOURCE: NRC MM 86-41)
COMPLETED 03-926-02 v Prior to conducting operations which would require the BBGT system to be operable, it will be verified operable in accordance with the Tech Specs.
(SOURCE: LER 86-021-01) 10-NOV-87 03-926-03 Resolve back draft damper issue on SBGT.
O (SOURCE: NRC IR 87-03) l l
O APPENDIX 10
23-Oct-87
-( J MAINTENANCE ISSUE: 03-927 l EXTENT OF IMBEDDED STEEL REINFORCING OF SAFETY.
RELATED CONCRETE WALLS DUE/ STATUS ACTION CLOSED 03-927-01 Contact the original PNPS contractor for a, search of construction records to establish that reinforcing bars were installed in safety related concrete walls in accordance with design drawings.
(SOURCE: NRC MM 86-41)
CLOSED 03-927-02 Use experience in mapping embedded steel reinforcing bars in concrete walls and in drilling for expansion anchor installation to.
validate design drawings for' concrete walls.-
(SOURCE: NRC MM 86-41)
() COMPLETED 03-927-03 Modify safety related masonry walls to withstand seismic.and'depressurization events.
(SOURCE: BECO LTR 81.058) i i
1 (h
s_/
\
j APPENDIX 10 l
_ _ _ _ ___ _ _ __________ ____. _ ___ l
}
i 4
,. 23-Oct-87 i I E}. . MAINTENANCE l
l ISSUE: 03-928 NON-SEISMICALLY QUALIFIED RELAYS (HGA & CFD) l DUE/ STATUS ACTION COMPLETED 03-928-01 Replace the GE type CFD relays with seismically qualified Westinghouse type SA-1 relays.
(SOURCE: LER'86-013-00) 02-NOV-87 03-928-02 l Identify HGA relays in use in safety related applications. !
(SOURCE: NRC MM 86-41) l l CLOSED 03-928-03 l Evaluate safety significance of HGA relay I i installations, and issue design change modification to replace unacceptable relays with qualified substitutes.
(SOURCE: NRC MM 86,-41)
CLOSED 03-928-04 Replace unacceptable,HGA relays with qualified substitutes.
(SOURCE: NRC MM 86-41) t
{
l I
(~
'(.)/ APPENDIX 10
\
23-Oct-87 l MAINTENANCE ISSUE: 03-929 ATWS/RECIRC MG SET FIELD BREAKER DUE/ STATUS ACTION CLOSED 03-929-01 Perform root cause analysis of ATWS RECIRC MG.
set field breaker which failed in June 1986.
(SOURCE: NRC MM 86-41) 1
. CLOSED 03-929-02
+ Perform root cause analysis of' recurring i breaker failures. )
(SOURCE: NRC MM 86-41) .i CLOSED 03-929-03 Conduct formal. industry survey of-failure l history and corrective action.
(SOURCE: NRC MM 86-41),
CLOSED 03-929-04 \
Perform aging and testing of lubricant.
() (SOURCE: NRC MM 86-41)
CLOSED 03-929-05 Investigate design change options (initiation of drive motor trip on ATWS signal - redundant to field trip; change spring design field breaker).
(SOURCE: NRC MM 86-41)
CLOSED 03-929-06 Investigate and recommend possible improvements to maintenance and testing practices.
(SOURCE: NRC MM 86-41)
L RFO-8 03-929-07 l Update breaker maintenance manual / procedure to L define use of special lubricants and enhance steps for making breaker adjustments.
(SOURCE: NRC MM 86-41)
CLOSED 03-929-08 Update root cause analysis and risk and reliability analysis relating to recirc MG set trip breakers.
k l- APPENDIX 10 l
23-Oct-87.
MAINTENANCE (SOURCE: -NRC MM 86-41)
CLOSED 03-929-09 Reassess corrective action to decide whether replacement of the recirc MG set field breaker.
would be more prudent than continuing trouble l shooting and repair efforts. i (SOURCE: NRC MM 86-41)
RESTART 03-929-10 Install PDC 87-30 to upgrade recirc MG set trip.
breakers.
i
} (SOURCE: NRC MM 86-41)
\
COMPLETED 03-929-11 . ;
Implement improvements to maintenance and testing practices recommended by Nuclear
(
Engineering Department investigation.
(SOURCE: NRC MM 86-41)-
.\
.[
L i
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i 1
'. APPENDIX 10
I l
l 1
23-Oct '( -)
MAINTENANCE j ISSUE: 03-930 HEAT DAMAGE TO PCIS CABLING-DUE/ STATUS ACTION j
, COMPLETED 03-930-01 .
Review operation of circuit involved and evaluate extent of damage.
(SOURCE: NRC MM 86-41)
COMPLETED' 03-930-02 0 Replace cable, relocate conduit and rapack O '
valve HOO100-107.
[ (SOURCE: NRC MM 86-41) .i l
CLOSED 03-930-03 '
Reinstall insulation on valve and affected '
steam lines.
(SOURCE: NRC MM 86-41)
COMPLETED 930-04 l -
Include in training an emphasis on importance i
(]) of early identification-and correction of material deficiencies.
(SOURCE: NRC MM B6-41)
COMPLETED 03-930-05 Assess effectiveness of-foregoing actions through continuing program of FEM trend analysis. !
(SOURCE: NRC MM 86-41)
APPENDIX 10
y -- . ,_,-
r
'q, i 23-Oct-87 MAINTENANCE '
. .'I ISSUE: 03-931 ,
c.
, BREAKER SETTING AND CONTROL COORDINATION-
~
- DUE/ STATUS ACTION n; -
s L CLOSED 03-931-01 .
l Initiate a temporary modification.to correct immediate breaker coordination l problem which.
L was not addressed in the original < design.
m . (SOURCE: NRC MM~86-41)
CLOSED 03-931 Initiate a full review of the breakor coordination issue. , T (SOURCE: NRC MM 86-41)
CLOSED 03-931-03 Develop a new and more comprehensive design ;
basis. '
(SOURCE:. NRC-MM 86-41) ,\
RESTART 03-931-04 Implement required PDC 8'J-15 changes to resolve-O- breaker coordination issue.
(SOURCE: NRC MM 86-41)
COMPLETED 03-931-05 Implement a Temporary Modification to-correct immediate breaker coordination problem which.
was not addressed in the original design.
(SOURCE: NRC MM 86-41)'
1 l
APPENDIX 10
9$hf M[' 9]m B .9 M.: ,
. * ,. /; ' y.9
. ,. ic. ,
/J j f
m, 23-Oct-87 MAINTENANCE y J.J \
ISSUE: 03-932 EMERGENCY. LIGHTING FOR SAFE SHUTDOWN PANELS
,,JHE/ STATUS ACTION l
/j,p}- COMPLETED 03-932-01 .
j
' ' ' ~
Provide adequate emergency lighting for four safe shutdown pane 12., , . , ,
. .c 1
(SOURCE: NRC IR 85-30-05)
' If -
g 1
t
'rf.
1
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i i
t O APPENDIX 10 mmm___.______m ___.-_m___a
4 C
23-Oct-87 f%,
MAINTENANCE ISSUE: 03-933 EPIC COMPUTER PROJECT DUE/ STATUS ACTION .l CLOSED 03-933-01 -
Write PDC to install EPIC cc Quter system to q monitor the RPS and-PCIS systems. {
(SOURCE: . CAL 86-10) !
RS + 120 03-933-02 l
-Instal 3.' EPIC computer system and have operable p by startup to monitor the RPS and PCIS systems.
Lo ;
i l
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L ( ,
d 1
I l
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l \
\ l l APPENDIX 10
23-Oct-87 l I
l (,
r')s MAINTENANCE' l l
_ ISSUE: 03-934 VATiVE TESTING DUE/ STATUS ACTION 15-DEC 03-934-01 Submit.a list of all pressure isolation valves at PNPS. For each valve, describe the periodic tests or other measures performed to assure the integrity of the valve as an independent barrier at the reactor coolant boundary along with the acceptance criteria for leakage, if any, and frequency cf test j performance.
(SOURCE: GEN LTR 87-06)
CLOSED 03-934-02 Incorporate seven year service requirement for ]
internals of ARI valves into PM program. l (SOURCE: 'NRC.IR 86-25)
\
l '
()
i i
l 1
-( ) APPENDIX 10 i
J
-q.
23-Oct-87. -i MAINTENANCE ,
i
. i
. ISSUE: 03-935 CONTAINMENT PRECdURE TRANSMITTERS DUE/ STATUS ACTION ;
- r. CLOSED 03-935-01 Replace the transmittersas per PDC 84-17.-
.(SOURCE: LER 85-011-00)
I l
l ,
I I t
I
\ 'i i
i I
l l
APPENDIX 10 1
r i
23-Oc-f)
MAINTENANCE ISSUE: 03-936 HYDROGEN WATER CHEMISTRY DUE/ STATUS ACTION
"" ~" RS + 105 03-936-01 Installpermanent'hydrogeninjectionsysli modifying operating and maintenance proci i
accordingly and train operators.
BECO LTR 86
!- (SOURCE:
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- APPEND:
1 I
n u h i f I' - -- 23-Oct-87 L : (- ~ -'
- MAINTENANCE
'~-
ISSUE: 03-937 MSIV PILOT POPPET VALVE' MODIFICATION l DUE/ STATUS ACTION j I CLOSED 03-937-01' l
,~ Investigate root cause and~ perform permanent.
modification of-MSIV-pilot poppets to ensure poppets remain screwed to poppet nuts during - i long term operation. i 6 (SOURCE: NRC IR 86-17-01'.7) i j ! 1 l .
\
l l l I
'b
,,qj APPENDIX 10 l-
)
!E l 23-Oct-87 [}
MAINTENANCE ISSUE: 03-938 MAINTENANCE REQUESTS TO BE CLOSED BEFORE RESTART DUE/ STATUS ACTION i CLOSED 03-938-01 !'
Provide the NRC with the process and criteria for determining those maintenance requests which require closure prior to restart. j (SOURCE: NRC MM 87-28) j 7 L. i
\
).- j
- i I
I 1
)
APPENDIX 10
I i i 23-Oct-87 1 MAINTENANCE j
< \
l ISSUE: 03-939 INCORRECT WOODWARD GOVERNOR SETTINGS l I DUEVSTATUS ACTION j l 1 COMPLETED- .03-939-01 Complete procedure for establishing Woodward Governor settings 30 days after the diesel generator has been declared operable,-and before startup. (SOURCE: NRC IR 87-26-01) I
\
() '
. I l
l 1 1 1 l (- O) APPENDIX 10 1 1
1 4 23-Oct-87 r MAINTENANCE ISSUE: 03-940 IMPROVING CONTROL OF VENDOR SUPPLIED INFORMATION l= l- QME/ STATUS . ACTION RS + 240 03-940-01 Evaluate the procedures for receiving vendor supplied information such as technical manual changes and drawing revisions within the Nuclear Organization and the practices in effect for controlling that information. Provide recommendations to correct identified i problem areas. l (SOURCE: SALP 86-99) l l
\
D) I l () APPENDIX 10
i l 23-Oct-87
~
MAINTENANCE ' ISSUE: 03-941 INADEQUATE REVIEW OF PLANT DESIGN' CHANGES. (PDCs) AND POST MODIFICATION PREOPERATIONAL TEST (PMPTs) , DUE/ STATUS ACTION RESTART 03-941-01 Establish a three man review group (with no concurrent duties) to review PHPTs. initiated for implementation during RFO 7. (SOURCE: NRC IR 87 33)
\
h V i l l l i l l l I L APPENDIX 10 t l- l 1 l l _.___________________________J
1 1 i 23-Oc;-57' x SURVEILLANCE-
~ l ISSUE: 04-001 j IMPROVE THE ADMINISTRATIVE CONTROL OF THE l SURVEILLANCE TESTING PROGRAM -
DUE/ STATUS ACTION
'30-NOV-87. 04-001-01 q centralise the control'of the surveillance data base and future changes within the Technical section. The Surveillance Test Program will be managed by the. Technical'section systems Group l
Leader. (SOURCE: SALP 86-99) COMPLETED 04-001-02 Conduct independent studies to analyse root i cause for missed reportable surveillance. test' events and initiatts actions to address root
-causes in the future.
(SOURCE: SALP 86-99) } RS + 150' 04-001-03 I ( ).. Clarify "once per cycle" test frequency with-NRC relative to containment Leakage Testing l 1 (LLRT, ILRT . Appendix J) and Tech Spec-related Equipment Surveillance requirements. , (SOURCE: NRC MM 86-30 (f) ) ! 15-NOV-87 04-001-04 Complete verification of the correct application of the once per cycle testing versus the once per refueling outage testing. (SOURCE: LER 86-016-00) 15-DEC-87 04-001-05 Revise the MSTP based on INPO Good Practice TS-410 to address missed surveillance tests, conflicting definitions of once/ cycle, inability of the surveillance tracking system !. to compensate for plant mode or for multiple component testing and clarification'of line responsibility. (SOURCE: NRC MM 86-41) i ( APPENDIX 10 C -- --
'l l
to. l l 23-Oct-87 I SURVEILLANCE 4 I
. COMPLETED 04-001-06 Identify and suggest corrective actions'to problems with surveillance requirements resulting from ambiguous' operating cycle related to Technica1' Specification surveillance requirements. 1 (SOURCE: NRC MM 86-41) -{
1 30-NOV-87 04-001-07 1 Improve and'aimplify MSTP database. (SOURCE: NRC MM 86-41)
] i 1
15-DEC-87 04-001-08 l Train personnel on new MSTP program and I procedures. { (SOURCE: NRC MM 86-41) 20-OCT-87' 04-001-09 Direct the implementation'of procedural changes j j to address ambiguous operating cycle relative j to Technical Specification surveillance ( requirements identified by surveillance \ i requirement study. j }. (SOURCE:' NRC MM 86-41)
')
l 1 I l l 1 l 1 l I 1 APPENDIX 10 i l l l I
L 23-Oct-87 SURVEILLANCE ISSUE:- 04-002 SURVEILLANCE PROCEDURES.
~DUE/ STATUS ACTION C'OMPLETED' 04-002-01
, Revise and apply Core Spray Functional Logic Test to include core spray start timer relays 14A-K, 14A&B.
(SCURCE: NRC IR 85-30-06). l CLOSED 04-002-02 Develop.and implement primary and-backup- '~ methods for determining N2 makeup capacity to the Primary Containment for purposes of quantifying containment. air volume leakage rate. l' (SOURCE: NRC IR 86-29-01)- l RESTART 04-002-03 Revise the surveillance procedures which- \ address the requirements of Technical
'\ Specification 4.5.C.1.a and use the revised-procedure to test the HPCI system.
(SOURCE: ' LER 86-012-00) RESTART 04-002-04 Rc'.*ise the surveillance procedure which addresses the requirements of Technical Specification 4.5.D.1.a and use the revised procedure to test the RCIC System. (SOURCE: LER 86-014-00) COMPLETED 04-002-05 Implement the testing requirements of Surveillance Procedure 8.M.1-30 for' instrument l calibration and functional tests for the recirc I pump trip / alt. rod insertion systems. (SOURCE: LER 86-019-00) 4 I COMPLETED 04-002-06 ! Conduct Surveillance Procedures 8.7.2.1 to I demonstrate that the Standby Gas Treatment ! System (SBGTS) fans automatically start and j j operate at 4000 CFM plus/minus 10% prior to i: core reload. l 1 l' APPENDIX 10 L i f i (. ! b _ __ - - - - . - - - - - - _
~
I i l l
)
23-Oct-87 SURVEILLANCE- 1 i (SOURCE: 'NRC IR 87-04-01) l RESTART 04-002-07 Conduct functional test of Rod Block Monitor 1
- and APRM trips per Tech Spec' Commitment. l (SOURCE
- .NRC IR 85-03-04)
)
RS + 30 04-002 ! Develop and implement primary and backup I methods for determining N2 makeup. capacity of L. the Primary Containment for purposes of ;
~
quantifying containment air volume leakage { rate. I (SOURCE: IFI 86-29-01) i i i l i l l \ l ($). 1 l 1 i i i f I s APPENDIX 10
.s
i s s - - 23-Oct-87 SURVEILLANCE
' ~
1 i l ISSUE: 04-003 l
-LOCAL LEAK RATE TESTS ADMINISTRATION AND j SURVEILLANCE DUE/ STATUS ACTION- {
CLOSED 04-003-01 Submit m' letter to the NRC requesting a clarification of the two year interval set ; forth in 10CFR50 App. J " Containment Leakage ' Control". (SOURCE: NRC MM 86-41). CLOSED 04-003-02 ! Two year maximum test interval will be. established for each LLRT component and included'in master surveillance tracking program until clarification is obtained.. (SOURCE: NRC MM e6-41) CLOSED 04-003-03 Updyte MSTP to include all components requiring () LLRT and insure two year maximum interval between tests of each component is properly i l controlled. (SOURCE: NRC MM 86-41) RESTART 04-003-04 Complete LLRT Surveillance Tests for LLRTs that- ' exceed the two year requirement. (SOURCE: NRC MM 86-41) RESTART 04-003-05 Perform LLRT on component to component basis and revise the MSTP to ensure that the 2. year maximum interval is properly applied to the LLRT test frequency. (SOURCE: NRC IR 86-21-08) CLOSED 04-003-06 Establish an LLRT Failure Analysis Teem as a standing entity to conduct root cause analysis and make recommendations to correct problems and prevent future failures. L (SOURCE: NRC MM 86-41) APPENDIX 10
I:
^*
'Q 23-Oct-87
\ '. SURVEILLANCE
'ILRT.+ 90 04-003-07 Analyse.cause of leaking Containment Isolation-Valves and develop. corrective / preventative.
l ~ maintenance actions. (SOURCE: NRC MM 86-41)
- CLOSED: 04-003-08 Revise the LLRT Surveillance' Procedures to add-a precaution regarding prior approval and documentation of. test. connection valve packing '
adjustments. (SOURCE: NRC-MM 86-41) j j COMPLETED 04-003-09 Initiate a Valve Betterment Program _to upgrade valves that have a history of maintenance.or-
. spare parts availability problems.
(SOURCE: NRC MM 86-41) CLOSED :04-003-10
. Verify that the MSIVs meet LLRT acceptance criteria by conducting surveillance Procedurd 8.7.1.6. !
{)' (SOURCE:' LER 86-011-00) o RESTART 04-003-11 i Evaluate the procedure for LLRT of feedwater check valves. Revise the procedure if necessary. (SOURCE: NRC MM 86-30) i RS + 150 04-003-12 ' Resolve surveillance scheduling problems associated with 4.16KV undervoltage relays surveillance. (SOURCE: NRC IR 86-21-08) J RS + 150 04-003-13 submit a Technical specification change request to clarify the definition of once per operating cycla. (SOURCE: NRC MM 86-41) RESTART 04-003-14 Implement the corrective / preventative maintenance actionu developed by the Valve Betterment Team and approved by management to APPENDIX 10 i
r I
?3-Oct-87 SURVEILLANCE.
correct the cause of. leaking. Containment Isolation-Valves.
-(SOURCE: .NRC MM 86-41)
't i
\
.O i
I L. ! fO xertuo1x 10 _________1_____._____._.________. __
r-- r i l . f l' 23-Oct-87
\_/ SURVEILLANCE l
ISSUE: 04-004 IN-SERVICE INSPECTION DUE/ STATUS ACTION CLOSED 04-004-01 Continue required ISI surface examination of safety related piping and identify unacceptable results in the NCR process. (SOURCE: NRC MM 86-41) ! 09-NOV-87 04-004-02 Perform ISI of pipe supports including expanding the sample of supports to be ; inspected when service induced problems are found. Identify unacceptable conditions found and verify completion cf corrective actions under NCRs. (SOURCE: NRC MM 86-41) f CLOSED 04-004-03 \ Perform an overall assessment of the RFO-6 and RFO-7.ISI program results for root cause. _O-NRC MM 86-41) (SOURCE: RS + 150 04-004-04 Results of IGSCC augmented inspection program sent to the NRC. (SOURCE: GEN LTR 84-11) , CLOSED 04-004-05 Cond'uct NDE inspections of welds rescheduled in the final report of the RFO-6 ISI. (SOURCE: FR-ISI) COMPLETED 04-004-06 Develop IST procedures for testing HPCI, RCIC and CS injection check valves to include positive verification that the disc travels to the seat promptly on cessation or reversal of flow and implement these procedures. (SOURCE: NRC IR 83-23-01) CLOSED 04-004-07 Inspect the welds identified in Generic Letter l 84-11 using the procedure and process derived D)(_ APPENDIX 10 w-_-_-- -__
23-Oct-87 , i]- SURVEILLANCE -
)
in accordance with GL84-11, BWROG and EPRI guidelines. ; (SOURCE: GEN LTR 84-11) ! NUREG+180 04-004-08 . Determine position relative to crack evaluation and repair criteria based upon NUREG 0313 Rev. 2 when issued by the:NRC. (SOURCE: GEN LTR 84-11)
'I
\
O.. I 9 O APPENDIX 10
^
23-Oct-87 SURVEILLANCE ISSUE: 04-005 CALIBRATION AND TESTING l DUE/ STATUS ACTION CLOSED 04-005-01 j Place the RER high pressure alarm switches on a- l once per cycle calibration schedcle. 4 (SOURCE: CAL 86-10) { l 30-OCT-87 04-005-02 . . Prepare and utilise-a procedure to periodically monitor RHRS pressures and temperatures, i (SOURCE: CAL 86-10) q COMPLETED 04-005-03 Schedule RHRs pressure gauge calibration every 'j refueling outage. (SOURCE: CAL 86-10) COMPLETED 04-005-04 I , Perform ~ leakage test, across RHRs.68 check I (f valves in accordance'with: Procedure 8.5.2.7 overy refueling outage. (SOURCE: CAL 86-10) RESTART 04-005-05 Complete the required relay. calibrations for voltage relays AS, A6 and the startup transformer. (SOURCE: LER 86-016-00) CLOSED 04-005-06 Evaluate protective relay setting and' test ! criteria and provide written criteria to the Maintenance Section. (SOURCE: NRC MM 86-41) CLOSED 04-005-07 Revise and update controlled documents for all i 4KV circuits and 480V load centers to reflect protective relay / breaker setting and testing. 1 (SOURCE: NRC MM 86-41) APPENDIX 10 l l l gg' - --
l l
.-- 23-Oct-87. l
);!
SURVEILLANCE RS + 60- 04-005-08 l Revise and update controlled. documents.for'.all ! 480V motor control centers to reflect L protective relay / breaker setting and-testing. (SOURCE: -NRC MM 86-41) l 04-NOV-87 04-005-09 Inspect the four upper' annulus drain. lines to
' determine that they are not plugged and that-I there is no drainage of water from :the drywell- j
-air gap. J (SOURCE: BECO LTR 87.074) .j i
- RFO-8 04-005 bJ Develop a surveillance procedure to inspect the L four' upper annulus drain lines each' refueling j b outage to determine that they are not plugged l 3
and that-there is no drainage of water.from'the 1 ! . drywell air gap. l (SOURCE:. BECO LTR 87.074)
\
p.h - h. l f I r "* l } .' [o I' APPENDIX 10 o l [? I L' ,, . . {
23-Oct-87 SURVEILLANCE ISSUE: 04-006 MEASURING AND TEST EQUIPMENT (MTEE) IMPROVEMENTS , 1 DUE/ STATUS ACTION COMPLETED 04-006-01 l Establish central METE issue areas for each discipline within maintenance. i (SOURCE: NRC MM 86-41) f COMPLETED 04-005-02 , Segregate out of calibration METE equipment from other METE equipment to prevent inadvertent use. (SOURCE: NRC MM 86-41) COMPLETED 04-006-03 Assign maintenance staff to manage the METE issue areas. (SOURCE: NRC MM 86-41) \ llg CLOSED 04-006-04 Station management spot check METE equipment through implementation of the management monitor Watch Program. (SOURCE: NRC MM 86-41) 20-NOV-87 04-006-05 Formalize a program for assessing the effectiveness of METE control using plant management tours emphasizing that function. (SOURCE: NRC MM 86-41) 31-OCT-87 04-006-06 Evaluate the effectiveness of METE control using a program of METE audits. (SOURCE: NRC MM 86-41) APPENDIX 10
l 1 23-Oct-87 SURVEILLANCE 1 I 1 ISSUE: 04-007 ECCS LOGIC SYSTEM FUNCTIONAL TEST IMPROVEMENTS i L DUE/ STATUS ACJJDH ; e I RESTART- 04-007-01 Revise as necessary ECCS Logic System . , functional tests and procedures required'for various mode switch positions. (SOURCE: 'NRC MM 86-41) q L J y 15-NOV-87 04-007-02 J Determine adequacy of simulated automatic > l
' actuation testing approach. I
~ (SOURCE: NRC MM 86-41)-
RESTART 04-007-03 1 Revise simulated automatic' actuation testing to incorporate the recommendations contained in the evaluation of adequacy report.
\
(SOURCE: NRC MM 86-41) I' RESTART 04-007-04 f k h-L
/'
Make appropriate ECCS Logic System functional ! test procedure changes to incorporate simulated-automatic actuation testing. (SOURCE: NRC MM 86-41) L i f% i APPENDIX 10
I l l i i I 23-Oct-87 FIRE PROTECTION . 1 ISSUE:- 05-001 ] STAFFING ISSUE - ESTABLISHING AND FILLING' KEY POSITION IN THE FIRE PROTECTION AREA DUE/ STATUS ACTION CLOSED 001-01 Centralize Fire Protection function at site through establishment of new group leader position to provide centralized management of the Fire. Protection program including direction-of resources, budget planning and control and long term planning of the program. (SOURCE: NRC MM 86-41) O i 4 (_/ APPENDIX 10
I l l 1
. 23-Oct-87
} ). FIRE PROTECTION ISSUE: 05-002 REDUCTION OF COMPENSATORY MEASURES DUE/ STATUS ACTION ]
CLOSED 05-002-01 , Inoperative Fire Protection systems requiring i compensatory measures are incorporated into the 2 plan-of-the-day. (SOURCE: NRC MM 86-41) COMPLETED 05-002-02 4 Inoperative systems requiring compensatory I measures receive daily review and are; assigned. t a priority level.- s (SOURCE: NRC MM 86-41) CLOSED 05-002-03 Inoperative systems requiring' compensatory measures receive priority treatment in the Plan-of-the-Day meetings. 1' (SOURCE: NRC MM 86-41) 1 CLOSED- 05-002-04 Establish fire watch compensatory measures action items report to assign' ownership of problem solutions. (SOURCE: NRC MM 86-41) i f () APPENDIX 10
- _ _ _ _ _ _ _ - _ _ _ _ - _ _ 1
R' . 23-Oct-87 i l FIRE PROTECTION
.. l
. ISSUE: 05-003 FIRE PROTECTION SURVEILLANCE PROCEDURES i l
DUE/ STATUS ACTION
.1:6-NOV-87 05-003-01 Develop and implement Temporary Procedures to ,
document the surveillance of Appendix R related l fire barriers. (SOURCE: SALP 86-99): l l i l l 1 { I l l 1 APPENDIX 10 {} I 1 _- . i
(b - K l-23-Oct-87 fh FIRE PROTECTION l ISSUE: 05-004 l HARDWARE ISSUE - FIRE BARRIERS / SEALS l i DUE/ STATUS ACTION l dLOSED 05-004-01 Perform fire barriers walkdown tb identify barriers and penetrations. (SOURCE: NRC MM 86-41) 16-NOV-87 05-004-02 Establish tracking mechanisms for tracking of new penetrations and for procedure revision. (SOURCE: NRC MM 86-41) CLOSED 05-004-03 Prepara specifications for procurement of equipment and material for existing penetration seals. (SOURCE: NRC MM 86-41)
^
CLOSED 05-004-04 Resolve (internally) which fire barriers are () required by Appendix R, Appendix A and Licensing Commitments. Prepare drawings identifying boundaries to be maintained. (SOURCE: NRC MM 86-41) 20-NOV-87 05-004-05 Submit Appendix R Licensing clarification if needed. (SOURCE: NRC MM 86-41) l 23-NOV-87 05-004-06 Upgrade non-Appendix R barriers as required. (SOURCE: NRC MM 86-41) APPENDIX 10
/}
.23-Oct-87 /~' .
( FIRE PROTECTION.
. ISSUE: 05-005 FIRE BRIGADE AND FIRE WATCH TRAINING DUE/ STATUS ACTION CLOSED 05-005-01 Eire permanent BECO Fire Brigade Instructor.
(SOURCE: NRC MM 86-41) l CLOSED 05-005-02 Revisa Nuclear Training Manual. requiring mandatory quarterly attendance-at fire brigade training. (SOURCE: NRC MM 86-41) CLOSED 05-005-03 Establish two drills per member each year, as requirement for fire brigade membership. (SOURCE: NRC MM 86-41) i i CLOSEL ' 05-005-04 Establish and maintain Fire Brigade qualification files. (T} s- . (SOURCE: NRC MM 86-41) 23-OCT-87 05-005-05 , Provide written scenarios to Fire Brigade Leader for drills. (SOURCE: NRC MM 86-41) CLOSED 05-005-06 Conduct critique at and of each drill. (SOURCE: NRC MM 86-41) CLOSED 05-005-07 Revise the Fire Brigade Training Drill Procedure to evaluate the performance of the participating brigade members as a team. (SCURCE: NRC MM 86-41) CLOSED 05-005-08 l Perform QA audit to assure the Fire Brigade Training is being implemented in accordance with approved procedures. (SOURCE: NRC MM 86-41) i I () APPENDIX 10 l
s 23-Oct-87 p, . . A FIRE PROTECTION ISSUE: 05-006 ADMINISTRATION OF FIRE PROTECTION PROGRAM. DME/ STATUS ACTION COMPLETED
. 05-006-01 Use routine submittals from~the Fire Protection Group and the Plan-of-the-Day process to establish priority treatment of Fire Protection Maintenance Requirements.
(SOURCE: NRC MM 86-41)
-CLOSED 05-006-02 1;stablish a fire protection system status board in the Control Room area.
(SOURCE: NRC MM-86-41) CLOSED 05-006-03 Establish a fire protection system Status Board for the Fire Protection Group Leader to assess ! operability. (SOURCE: NRC MM 86-41)' O CLOSED 05-006-04 Assess program effectiveness in a formalised , monthly report for upper management. (SOURCE: NRC MM 86-41) i l i CLOSED 05-006-05 Train appropriate station and engineering personnel in existing corrective action program including use of FEMRs. (SOURCE: NRC MM 86-41) CLOSED 05-006-06 Assess effectiveness of Corrective Action Program Training, (specifically F&MR use) using i performance indicators 1 (SOURCE: NRC MM 86-41) CLOSED 05-006-07 Establish a Fire Protection Coordinator to assist Barrier Walkdown Team and Watch Engineer in identifying Fire Watch postings for identified deviations. (SOURCE: NRC MM 86-41) APPENDIX 10 W *
;1:
23-Oct-87 l (). FIRE' PROTECTION ISSUE: 05-007 APPENDIE R MODIFICATIONS DUE/ STATUS ACTION
$3-NOV 05-007-01 Repair degraded seals and install new seals where required in Appendix R Barriers.
(SOURCE: NRC MM 86-41) 4 J 16-NOV-87 05-007-02 Evaluate design to determine the extent of 1 fuse-to-breaker coordination, resultant actions, and modify circuitry as necessary. , (SOURCE: BECO LTR 83.070) i l CLOSED 05-007-03 j Provide suppression pool temperature and level I indications independent of a control room fire.. (SOURCE: BECO LTR.83.070) 15-NOV-87 05-C07-04 l i 1 Modify contro1' circuit for valve MO-1001-47 so that it will not spuriously operate by a fire f
~
condition in the areas where the control
~
j circuits for redundant valve MO-1001-50 are , (SOURCE: .BECO LTR 83.070) 30-OCT-87 05-007-05 Install sprinkler system at elev 51 and 23 of RX building to address App. R separation requirements. BECO LTR 83.070) .l (SOURCE: CLOSED 05-007-06 Revise alternate shutdown procedure 2.4.143 to ' reflect recently installed modifications and NRC concerns. (SOURCE: BECO LTR 83.194) CLOSED 05-007-07 Modify torus water temperature instrumentation. (SOURCE: BECO LTR 83.281) h APrENo1x 10 (:) l
23-Oct-87 FIRE PROTECTION l 15-NOV-87 05-007-08 Reroute power and control cable for A & B diesel generator fuel oil transfer pumps. (SOURCE: BECO LTR 83.281) 15-NOV-87 05-007-09 Reroute power cables feeding MCC B18 out of torus compartment. (SOURCE: BECO LTR 83.281) CLOSED 05-007-10 Install i hour rated fire wrap on newly installed additional torus water temperature instrumentation in the torus compartment. (SOURCE: BECO LTR 84.049) 23-NOV-87 05-007-11 Remove wood scaffolding from the torus fire zone 1.30A except that required for surveillance testing. All such remaining scaffolding will be either pressure treated fire retardant (UL/FM approved) or painted with a listed and approved fire retardant coating. () (SOURCE: BECO LTR 86.110) 06-NOV-87 05-007-12 Provide to NRC detailed information regarding fire protection work expected to be outstanding as of plant startup, and those compensatory measures expected to be in place at startup. (SOURCE: NRC MM 87-28) i APPENDIX 10
I r 23-Oct-87 ()' MISCELLANEOUS ISSUE: 06-001 l NUCLEAR ORGANI5ATION IMPROVEMENTS l
' \
J DUE/ STATUS ACTION l f dLOSED 06-001-01 j Eliminate dual reporting chain with site organizations reporting to both the Outage Management Director and the Nuclear Operations-Manager. (SOURCE: SALP 86-99) CLOSED 06-001-02 Fill all outstanding key management positions. (SOURCE: SALP 86-99) O f APPENDIX 10 ()
1 23-Oct-87 !' / MISCELLANEOUS ISSUE: 06-002 . NULTIPLE ADMINISTRATIVE DATA BASES / TRACKING SYSTEMS USED IN NUCLEAR ORGANIZATION DO NOT INTERFACE / INTERACT EFFICIENTLY l
\
DUE/ STATUS ACTION RFO-7 +730 06-002-01 Capture all administr.itive work items into (minimum required) i 43ractive data bases. (SOURCE: NRC MM ' 8 6-32 ( f) ) , 8 () APPENDIX 10
23-Oct-87 l (): MISCELLANEOUS ISSUE:- 06-003 IMPROVE THE' LEGIBILITY OF DRAWINGS DUE/ STATUS ACTION dLOSED 06-003-01 Publish drawing-legibility standards. (SOURCE: NRC MM 86-41) CLOSED 06-003-02 Implement a. quality check of all new vendor drawings and reject illegible drawings. (SOURCE: NRC MM 86-41) CLOSED 06-003-03 Upgrade existing drawings as drawing revisions- ;
)
occur. (SOURCE: NRC MM 86-41) CLOSED 06-003-04 Examine prints made from all existing aperture ! cards and identify poor quality aperture cards-
<G and poor quality original prints.
V -(SOURCE: NRC MM 86-41) CLOSED 06-003-05 l Prioritizing poor quality original drawings for l restoration. ! (SOURCE: NRC MM 86-41) l l CLOSED 06-003-06 ! Prepara plan and schedule for drawing ! restoration work. (SOURCE: NRC MM 86-41) CLOSED 06-003-07 Upgrade quality of all equipment in the drawing processing cycle. (SOURCE: NRC MM 86-41) CLOSED 06-003-08 Implement 100% quality inspection of new { aperature cards sent to the Document control Center. (SOURCE: NRC MM 86-41) j i () APPENDIX 10 !
)
23-Oct-87 l () . MISCELLANEOUS l CLOSED 06-003-09 , I Train clerical staff in drawing legibility' requirements. (SOURCE: NRC-MM 86-41) C.LOSED 06-003-10
- Issue-Work instructions and initiate monthly q random sampling of DCC issued drawings to !
monitor. operator and equipment performance. (SOURCE: NRC MM 86-41) - l LO u () APPENDIX 10
1
. A. ~)
23-Oct-87 MISCELLANEOUS ( 1 ISSUE: 06-004 ! IMPROVE THE CONTROL OF PROCEDURE ISSUE TO ENSURE THAT ONLY THE LATEST REVISION OF A PROCEDURE IS ISSUED bUE/ STATUS ACTION CLOSED 06-004-01 Devise controls to ensure that only the latest revisions of NOD procedures are issued. (SOURCE: SALP 86-99) 9 0 APPENDIX 10 t( ) i l l l - _ _ _ _ _ _ _ _ _ _ _ _ J
- r. 1 f,,,
23-Oct-87 MISCELLANEOUS ; ISSUE:1 06-005-COMPLIANCE OF EMERGENCY ACTION LEVELS WITH
'NUREG-0654 DUE/ STATUS ACTION CLOSED 06-005-01 Review EALs against NUREG-0654..
(SOURCE: NRC MM 86-41) CLOSED 06-005-02: Revise Procedures 5.7.1.1, 5.7.1.2,-5.7.1.3, 5.7.1.4 and 5.7.1.5 to comply with NUREG-0654. (SOURCE: NRC MM 86-41) 4 CLOSED 06-005-03 Revise lesson plans as necessary for operator training on EALs. (SOURCE: NRC MM 86-41) CLOSED 06-005-04 Conduct operator training on revised EAL procedures. O, (SOURCE: NRC MM 86-41) COMPLETED 06-005-05 Revise, print and distribute' wall mounted EAL displays. (SOURCE: NRC MM 86-41) H
\
() APPENDIX 10 l
23-Oct-87 MISCELLANEOUS ISSUE: 06-006 MAINTENANCE OF POSITIVE PRESSURE AT THE EOF UNDER EMERGENCY CONDITIONS DUE/ STATUS ACTION CLOSED 06-006-01 Install manometer for continuous read-out of EOF positive pressure values. (SOURCE: SALP 86-99) CLOSED 06-006-02 Draft and implement E.P. Work Instruction to require regular verification of positive pressure at EOF. (SOURCE: SALP 86-99) O i l 4 I I () APPENDIX 10
r------------- - - - - - ----
)
i
~ .
23-Oct-87 1 SECURITY .' { ISSUE: 07-001 SECURITY ORGANIZATIONAL AND STAFFING IMPROVEMENTS DUE/ STATUS ACTION CLOSED 07-001-01 security Group reporting line changed from plant management to vice. President Nuclear Operations (currently senior V. P. level). ] (SOURCE: SALP 86-99) { 1 CLOSED 07-001-02 Establish Security Operations Group.
- (SOURCE: ~NRC MM 86-41)
CLOSED 07-001-03 ; Add one BECo Security Supervisor per' shift. NRC MM 86-41) (SOURCE: CLOSED 07-001-04 Establish Administration, Compliance and () Technical specialist positions and fill positions with permanent BEco employees. (SOURCE: NRC MM 8C -41) CLOSED 07-001-05 Establish three new supervisory positions in the plant. areas of Main Gate Access, Central Alarm station and secondary Alarm station. (SOURCE: NRC MM 86-41) COMPLETED 07-001-06 Increase the total security force. (SOURCE: NRC MM 86-41). COMPLETED 07-001-07 Reduce the supervisor-to-patrolman ratio from j
)
1-20 to 1-10 or less. (SOURCE: NRC MM 86-41) i COMPLETED 07-001-08 ! Perform root cause analysis of continued l weaknesses in follow-up on problems. (SOURCE: NRC MM 86-41) g' APPENDIX 10 l 1 i
--- _ -~--me .'?-
}
'l 23-Oct-87
] '! ) SECURITY ISSUE: 07-002 , IMPROVE THE SECURITY SYSTEMS-IN ORDER'To ' INCREASE SECURITY' EFFECTIVENESS AND REDUCE RELIANCE ON COMPENSATORY MEASURES. DUE/ STATUS ACTION COMPLETED 07-002-01 Conduct a system level requirements analysis to identify improvements required in the hardware. (SOURCE: NRC MM 86-41) COMPLETED 07-002-02 Corrective maintenance to security' equipment and hardware is scheduled to be complete prior to restart. (SOURCE: SALP 86-99) CLOSED 07-002-03 Monitor the material status of the security system. A security staff technical specialist will track the outstanding maintenance items, monitor preventive maintenance and surveillance () status and establish the primary focus for major modifications of the security systems. (SOURCE: NRC MM 86-41) COMPLETED 07-002-04 Prioritize the Security maintenance requests. Establish controls to ensure' proper prioritization of future security maintenance , requests. (SOURCE: NRC MM 06-41) > COMPLETED 07-002-05 Resident NRC Inspector provided with expected completion date for Engineering evaluations of the scope of security equipment improvement. (SOURCE: NRC MM 86-30) 28-FEB-88 07-002-06 Install plant design changes for CCTV, fence and intrusion detection improvements. (SOURCE: NRC MM 86-41) APPENDIX 10
1 . 1 ji T 23-Oct-87 r
/ SECURITY 25-OCT-87 07-002-07 .
Develop a security equipment preventive maintenance. program. (oOURCE: NRC MM 86-41) COMPLETED 07-002-08 Conduct an evaluation of the continual i utilization of. compensatory measures. (SOURCE:- NRC MM 86-41) COMPLETED 07-002-09 Increase management's awareness of the use of compensatory measures. , NRC MM 86-41) (SOURCE: COMPLETED 07-002-10 Discuss with the responsible individual any-compensatory measures in existence greater than 30 days to ensure resolutions-are promptly planned and scheduled. 1 (SOURCE: NRC MM 86-41) CLOSED 07-002-11 Inform NRC of new dates on installation plans
'O for security modifications.
(SOURCE: NRC MM 86-41) i 1 APPENDIX 10
23-Oct-87 !
) SECURITY ,
ISSUE: .07-003-PROCEDURE / INSTRUCTION CHANGES AND TRAINING ! REQUIREMENTS RESULTING FROM SECURITY PROGRAM REVIDIONS bOE/ STATUS ACTION 30-OCT-87 '07-003-01
' Review and update / revise security procedures and instructions.
(SOURCE: NRC MM 86-41) { 31-OCT-87 07-003-02 Review / revise the Security Training & . j Qualification (TEQ) Plan to ensure it remains current and reflects actual security practices. , Revise training materials to reflect TEQ l changes. j (SOURCE: SALP 86-99) J l
)
APPENDIX 10 .( ) l
llll f. 23-Oct-87 QUALITY ASSURANCE ISSUE: 08-001 ) IMPROVE THE RESPONSE TO QA CORRECTIVE ACTION l PROGRAM ) DUE/ STATUS ACTION CLOSED 08-001-01 . Establish weekly meetings between QA Manager and Plant Manager to discuss QA Corrective Action problems. . . (SOURCE: NRC MM 86-22) CLOSED 08-001-02 Revise the QA Corrective Action Program to incorporate non-regulatory problems. (SOURCE: NRC MM 86-22-D(5)) CLOSED 08-001-03 Revise the BEQAM to ensure that DRs get~ timely handling in the QA corrective Action Program. (SOURCE: NRC MM 86-22-D(1)) r~g CLOSED 08-001-04 (/ Revise the BEQAM to include requirement for i Vice-President notification 15 days before expiration of 90-day corrective action limit. (SOURCE: NRC MM 86-41) CLOSED 08-001-05 Revise BEQAMlto include requirement that unresolved corrective Action issues are automatically elevated to top management. (SOURCE: NRC MM 86-41) COMPLETED 08-001-06 Establish requirement that Vice-Presidents issue written re;,.rimands to department managers who fail to mest deficiency report commitments. (SOURCE: NRC MM 86-41) , CLOSED 08-001-07 Revise Nuclear Organization Procedure (NOP) to incorporate BEQAM Corrective Action requirements. (SOURCE: NRC MM 86-41) () APPENDIX 10
F l
~
L-
.o I
23-Oct-87 ) QUALITY ASSURANCE i l-CLOSED 08-001-08 . . u Train nuclear organization personne1Lon the l Corrective Action Program and. associated NOP. f (SOURCE: NRC MM 86-41) i
?
CLOSED' 08-001-09 ' Revise'QA department deficiency report . procedure to conform to the BEQAM fcr the handling of second-responses to deficiency reports. , (SOURCE: NRC MM 86-41) .! ( !:' CLOSED 08-001-10 l l Revise the QAD Deficiency Report procedure .l description to better define the. term l l-HsignifiCantH. 1 I
-(SOURCE: NRC MM 86-41)
CLOSED 08-001-11 Assess organizational and corrective action ; program effectiveness by using key performance ; indicators and periodic QAD reports. j (SOURCE: NRC MM 86-41)
.j $[). .
1 i i i ( e e APPENDIX 10
23-Oct-87 e (_/ QUALITY ASSURANCE ISSUE: 08-002 IMPROVE QA STAFFING DUE/ STATUS ACTION h3-NOV-87 08-002-01
- Fill two vacancies on the ten-member on-site surveillance Group with permanent BEco employees.
(SOURCE: BECO LTR 87.130) 03-NOV-87 08-002-02 Fill three new personnel slots in the Quality Assurance Department with permanent BEco employees:
- One auditor with health physics expertise;
- Two Quality control personnel to inspect radwaste shipments.
(SOURCE: BECO LTR 87.130) a f 1 l l () APPENDIX 10 l l
't n
d 23-Oct-87 r~
'; LICENSING ISSUE: 09-001
' IMPROVEMENTS IN THE CONTENT AND ACCURACY OF THE TECHNICAL SPECIFICATION DUE/ STATUS ACTION COMPLETED 09-001-01 Review Technical specifications to identify incorrect specifications and submit request to NRC for those revisions required by startup.
(SOURCE: S7 LP 86-99) 20-NOV-87 09-001-02 Establish a list of criteria for Technical-specification changes which will include ! clarity of basis, action statement /LCO agreement, precise wording. (SOURCE: NRC MM 86-41) CLOSED
- 09-001-03 schedule Technical specification review and upgrade for those Tech spec amendments required before startup.
( (SOURCE: NRC MM 86-41) 20-NOV-87 09-001-04 Develop schedule for streamlining Technical
' specification review process.
(SOURCE: NRC MM 86-41) 20-NOV-87 09-001-05 l Establish a schedule of post-startup Technical ' specification changes prior to startup from RFO-7. (SOURCE: NRC MM 86-41) CLOSED 09-001-06 submit Technical specification change request j to eliminate testing of redundant ECCS equipment. (SOURCE: NRC MM 86-41) CLOSED 09-001-07 submit Technical specification change request to reduce frequency of MO 1001-28B and 29B valve stroking. APPENDIX 10 (/ (
i:
.23-Oct-87
' LICENSING I (SOURCE: CAL 86-10) i
- CLOSED 09-001-08 Review the QA finding on ATWS functional test.
Determine if Technical Specification Table ! 4.2.G should be changed to reference Note (7). l (SOURCE: NRC IR 86-25-12) i' O 5 i i i f APPENDIX 10 j O. i 1 4 i
<=
l I Oct-87 I , LICENSING 1 ISSUE: 09-002 RESPONSE TIME TO NRC INFORMATION REQUESTS DUE/ STATUS ApTION CLOSED 09-002-01 )' Establish and proceduralise a system to ensure
- timely response to NRC information requests.
(SOURCE: SALP 86-99) COMPLETED 09-002-02 Complete the review of the NRC Safety Evaluation (April 30, 1986) and verify all statements accurately reflect condition of the l Plant at the end of the inspection period. t Report any discrepancies to NRC. (SOURCE: NRC IR 86-25-06) 09-002-03 ! CLOSED Evaluate and report MSIV leakage rates. (SOURCE: CAL 86-10) O () APPENDIX 10
23-Oct-87. TRAINING ISSUE:- 10-001 OPERATOR TRAINING
-DUE/ STATUS ACTION h0-OCT-87 10-001-01 Train operations staff (Ros, SRos . and STAS) in
' use of revised Emergency Operating Procedures. (SOURCE: NRC MM 86-32-C) CLOSED 10-001-02 Conduct 20 hours of hands-on-training per shift c on PNPS simulator emphasizing ~ normal plant' startup and operating transients. (SOURCE: NRC MM 86-32)
~ CLOSED 10-001-03 Conduct operator training on the Radiological Environmental Technical Specifications (RETS) per Amendment is9. ,
(SOURCE: SALP 86-99) !
/ CLOSED- 10-001-04 Train operations staff on RHR intersystem
' leakage issue.
(SOURCE: CAL 86-10) i () APPENDIX 10
i l 23-Oct-87 I (m)
'~'- TRAINING ISSUE: 10-002 ADMINISTRATIVE IMPROVEMENTS TO THE OVERALL TRAINING PROGRAM DUE/ STATUS ACTION CLOSED 10-002-01 Revise the Nuclear Training Manual to more clearly define required participation in the licensed operator / manager requalification training program.
(SOURCE: .SALP 86-99) CLOSED 10-002-02 Revise the Nuclear Training Manual requalification training in the area of , preparing, administering and evaluating oral i examinations. (SOURCE: SALP 86-99) 30-OCT-87 10-002-03 Revise the Nuclear Training Manual, Section (f 3.1.7, for written examination to ensure that procedural knowledge of system operation is , reflected in future examinations. ' (SOURCE: SALP 86-99) I 1 I 1 i N- APPENDIX 10
I I 23-Oct-87 () TRAINING ISSUE: 10-003 MAINTENANCE PERSONNEL TRAINING AND EDUCATION
-DUE/ STATUS ACTION dLOSED 10-003-01 i Develop, issue and use training module for.
field supervision / monitoring activities. (SOURCE: NRC MM 86-41) CLOSED 10-003-02 Conduct training and continuing education of maintenance personnel assigned to work on Limitorque MOVs. (SOURCE: NRC MM 86-41) O l ; h APPENDIX 10 , ( i i i 4
- - - - _ _ _ _ _ _ i
23-Oct-87 ENGINEERING If ISSUE: 11-001 SAFETY EVALUATION OF DRYWELL INSULATION
'DUE/ STATUS ACTION COMPLETED 11-001 Review the 10 CFR 50.59 evaluation relative to the dryvell insulation replacement work
. accomplished during RFO 6.
(SOURCE: GEN LTR.85-22) l i U I I APPENDIX 10 t ) A--- . _ . - _ _ _
l 23-Oct-87 ENGINEERING ( 4 ISSUE: 11-001 RHR CHECK VALVE POSITION MONITORING , DUE/ STATUS ACTION CLOSED 11-002-01 Revise safety evaluation (1959 to clarify-intent (address reduction in RER flow). (SOURCE: CAL 86-10) CLOSED 11-002-02 Evaluate new RHRS and core spray check valve position monitoring system options as an improvement over the original designs. (SOURCE: CAL 86-10) i l 4 4 APPENDIX 10
t i 23-Oct-87' ,
'- ENGINEERING.
ISSUE: 11-004 VARIOUS DRAWING DISCREPANCIES DUE/ STATUS ACTION { 1 dLOSED 11-004-01' Resolve identified specific wiring and print discrepancies. (SOURCE: CAL 86-10) 1 i i I fO - APPENDIX 10 l l I
23-Oct-87 () ENGINEERING ISSUE: 11-005 CHECK VALVES DESIGN REVIEW 1 DUE/ STATUS ACTION dOMPLETED 11-005-01 Evaluate the feasibility of replacing or redesigning RHRS and Core Spray check valves to provide positive position indication. (SOURCE: CAL 86-10) CLOSED 11-005-02 Determine the test configuration and the acceptance criteria for test of pressure drop capability of the RERS 1001-68A and 68B check valves. (SOURCE: CAL 86-10) COMPLETED 11-005-03 Conduct the pressure drop capability test of , the RERS 1001-68A and 68B check valves. (SOURCE: CAL 86-10) l () l () APPENDIX 10 (
23-Oct-87 m ENGINEERING
. (_)
ISSUE: 11-006 INVESTIGATE CAUSE OF MODE SELECTOR SWITCH ANOMALIES DURING POWER ASCENSION DUE/ STATUS. ACTION dLOSED 11-006-01 Develop a procedure to conduct a limited power ascent and descent through the portion of power ascension when the reactor mode switch is repositioned from run mode to start-up mode. This test may confirm the root cause analysis if anomelles recur. (SOURCE: CAL 86-10) O { l I I l l 1 APPENDIX 10 i( )
__-___m_ _ _ _
23-Oct-87 ENGINEERING i L ISSUE: 11-007 l DESIGN ANALYSIS OF HPCI-TURBINE EIHAUST STOP. CHECK VALVE REPLACEMENT
. DUE/ STATUS ACTION CLOSED 11-007-01 Conduct design analysis to support the replacement of HPCI turbine exhaust stop check valve 2301-74.
(SOURCE: NRC IR 85-30-10) O r APPENDIX 10
= .
23-Oct-87 () . ENGINEERING ISSUE: 11-008 USE OF NCR AND PDC PROCESSES TO PERFORM PLANT CHANGE / WORK l DUE/ STATUS ACTION 20-NOV-87 11-008-01 Determine reason for use of NCR process rather than PDC process and correct. (SOURCE: SALP 86-99) CLOSED 11-008-02 Establish a procedure to formalize the LER l submittal and review process. (SOURCE: SALP 86-99) U i 4 () APPENDIX 10
APPENDIX 11 CHANGES TO REGULATORY COMMITMENTS This appendix summarizes changes to regulatory commitments from source documents referenced in Appendix 10. The meaning of.the term " commitment" as used herein has been expanded to include those statements by Boston Edison in earlier correspondence on the status of actions, as well as statements of actions to be undertaken to address specific concerns. In - some cases, reports of status were made that indicated an anticipated completion date for a commitment action later than the date of the status report. Where that date has not been met, I the item ' is not considered a commitment change unless Boston l Edison has scheduled completion of the action after restart. l Each change in this appendix will name the source document to which the change applies. Separate statements of the commitment or status as it was originally written, and of the changes are included. An explanation of the need for each change is also provided. Appendices 8, 9 and 10 have been revised to reflect the change in the commitment in cases where the action statements were affected. y e O 4
.. i n 1 !
CHANGE TO MANAGEMENT MEETING 86-41 ; MAR 87 and 6 MAY 87 STATUS LETTERS )
SUMMARY
This change revises 'the predicted complete implementation date for r revision of the Master Surveillance Tracking Program (MSTP). ORIGINAL COMMITMENT / STATUS: Action
" Revise the MSTP based on INPO Good Practice TS-410 ' Surveillance and ' Periodic Task Scheduling Program' to address (a) through (c)."
Status Both letters contain wording to indicate that completion was expecf.ed before startup.from RFO-7.
,e .
'O : CHAbl3E:
.Chartjge the status to indicate that completion is expected on.15 Decnnber 1987.
9 SOUFtE OF COMMITMENT / STATUS: 4* Boston Edison letters 87-039 of 1 MAR 87 and 87-070 of 6 MAY 87 (status reports on Management Meeting 86-41) issue 4.A.1. l REASON FOR CHANGl* , f Revision of the MSTP is not required to be completed before startup. However, the MSTP has been revised based on INPO Good Pra):tice TS-410 and both the old and new MSTPs are being run in parallel until the new system has been thoroughly proven.
2 I Q CHANGE TO MANAGEMENT MEETING 86-41, 6 MAY 1987 STATUS LETTER
SUMMARY
The change clarifies ambiguous wording concerning the hiring of a Fire Brigade instructor. ORIGINAL COMMITMENT / STATUS: Action "S. Hire dedicated fire brigade drill instructor
- 6. Hire permanent BECo fire brigade instructor" Status "5. Completed
- 6. Recruitment in progress" ca^"os:
O Change the Item 5 Action staterient above to remove the word
" drill". The status of item 6 should include the words, "The new employee will replace the contractor currently filling the Fire Brigade Instructor position".
SOURCE OF COMMITMENT / STATUS: Boston Edison letter 87-070 of 6 May 1987 (status xeport on Management Meeting 86-41) issue 7.A.1. REASON FOR CHANGE: The wording of the action and status statements could lead a That reader to conclude that two individuals were to be hired. The status of this item on 6 May 1987 was was never intended. that a contractor was filling the position while a permanent BECo employee was being sought. A permanent BECo employee now fills the position. O
1 3 CHANGE TO MANAGEMENT' MEETING 86-41
.1 MAR 1987 AND'6 MAY 1987 STATUS LETTERS
SUMMARY
Th'is. change clarifles' .the wording- describing steam' lines requiring reinsulation.
' ORIGINAL COMMITMENT / STATUS:
' Action
" Reinstall inse,lation on valve and main steam line."
i CHANGE: Change the words " main steam line" to read "affected steam line". l' D .. V SOURCE OF COMMITMEN'T'/ STATUS: Boston . Edison letters 87-039 of 1 March 1987 and 87-070 of 6 May 1987 (status ' reports on' Management Meeting 86-41) issue 3.B.6. REASON FOR CHANGE: To clarify the wording of the commitment. The words " main steam line", imply it was part of the main steam header. The affected piping is a 3 inch line, " Steam Supply to Recombiner Room". i I-o O l
-_J_,v-__-__--.
l 4 n CHANGE TO MANAGEMENT MEETING 86-41. 1 MAR 87 STATOS LETTER'
SUMMARY
This change- clarifies the . status reported earlier on the accomplishment of drawing legibility work done in accordance with revised procedures. ORIGINAL COMMITMENT / STATUS: Action "1.a. Publish drawing legibility standards Implement a quality check of all new vendor drawings 1.b. reject illegible' drawings 1.c. Upgrade existing drawings as necessary as. revisions occur." Stabus
-O "- co vtetea redru rv, 1987
- b. Completed February, 1987 - continuing program in place
- c. Completed February, 1987 - continuing program in place" CHANGE:
The status is more precisely reported as follows:
"a. Drawing legibility standards were published in June 1986 and were in effect on 1' March 1987.
b&c. Work on quality check of new drawings and upgrading of existing drawings commenced in August 1986. Programs to review new and existing drawings were in place in February 1987. Procedure revisions specifying actions for drawings with legibility problems were issued on 16 March 1987." SOURCE OF COMMITMENT / STATUS: Boston Edison Ietter 87-039 of 1 MAR 87 (status report on Management Meeting 86-41) issue 1.A.4. i L l 1 l _j
4 - Page 2 REASON FOR CHANGE: i The purpose of this , change is to clarify the status of procedures NOP 84A7 and NMSD 6.02, which govern drawing legibility work, and the work itself, on 1 March 1987. Drawing legibility standards were published in June 1986. Those standards were in effect and in use on 1 March 1987. Procedure NMSD 6.02, which contains the standards, was revised and issued on 11 March 1987 to include drawing rejection procedures. The legibility standards remained unchanged in the March 1987 version. DR 1565 dated 12 August 1986, started the process and the work of actions 1.b and 1.c. These programs, using proper standards, were in place in February 1987 and were the basis of the status reported on 1 March 1987. Revisions to Procedure NOP 84A7 were in progress specifying actions to be taken with drawings with legibility problems. This revision was issued on 16 March 1987. O 1 l 4 O
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5 L 1 O- CHANGE TO MANAGEMENT MEETING 86-41, l 1 MAR & 6 MAY'87 STATUS LETTERS j and SALP 86-99 RESPONSE LETTER l l
SUMMARY
This. change.revisesacommitmenttoholdregularmeetingsbetween r Fire Protection and Maintenance managers. l ORIGINAL COMMITMENT / STATUS: In all three source documents, Boston Edison committed to regular (initially weekly) meetings between Fire Protection and Maintenance for the purpose of prioritizing fire protection equipment maintenance work. ; CHANGE: Prioritization of Fire Protection maintenance items will be
.I accomplished using the Plan of the Day process.
. SOURCE OF COMMITMENT / STATUS:
Boston Edison Letter 87-83 of 22 May 1987 (Response to SALP 86-99 report); Boston Edison Letters 87-070 of 6 May 1987 and 87-039 of 1 March 2,987 (status reports of Management Meeting 86-41) issue 7.A.3. REASON FOR CHANGE: The weekly meetings of the original commitment were initially conducted for the purpose stated. Changes to upgrade the Maintenance Plan of the Day meeting format and content made it practical to properly address fire protection maintenance issues in the daily maintenance planning meeting. The dedicated fire protection maintenance meetings therefore are redundant and have been discontinued.
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'f CHANGE TO MANAGEMENT MEETING 86-41, ,
b' 1 MAR & 6 MAY 87 STATUS LETTERS
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SUMMARY
Th,is change cancels a commitment to train Senior Reactor i Op'erators to function in a Reactor Operator capacity during startup. 1 ORIGINAL COMMITMENT / STATUS: Action
" Temporarily supplement existing R.O. staff with SRos to meet f l
overtime guidelines." i Status will receive R.O. refresher training prior to "Four SROs 1 startup." O V CHANGE: Cancel this commitment. l SOURCE OF COMMITMENT / STATUS: Boston Edison Letter 87-039 of 1 March 1987 (status report on Management Meeting 86-41) issue 1.A.1. [This item also appears essentially unchanged in Boston Edison Letter 87-070 of 6 May 1987.] l REASON FOR CHANGE: 1 I The additional ROs are not required to support the four shifts to be used for power ascension. Newly licensed ROs will be fully qualified prior to completion of power ascension. This will allow transition to six shift operation without using SROs as Ros to meet overtime guidelines. O
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- CHANGE TO MANAGEMENT MEETING 86-41. 6 MAY 87 STATUS LETTER
SUMMARY
This change clarifies. the earlier reported status of the effort to streamline the Technical Specification change process. j 1 ORIGINAL COMMITMENT / STATUS: i Action .
" Streamline the technical specification change process."
Status
" Completed" CHANGE:
The status is more precisely stated as follows: "The draft procedure was in use in May 1987. The final procedure is in the review process, with approval expected by 20 November 1987". SOURCE OF COMMITMENT / STATUS: Boston Edison Letter 87-070 of 6 May 1987, (status report on Management Meeting 86-41) issue 10.A.1. J REASON FOR CHANGE: To clarify the status provided on . 6 May 87 concerning the completeness of the action. The report that the action was completed is not precise. It was made before a clearly defined acceptable standard for judging the completeness of actions had been established. Current standards in effect for closing items l in the regulatory commitments appendix (Appendix 10) include l precisely worded completeness acceptance criteria, clearly I defined supporting documentation requirements, a knowledgeable l independent review and two management certification signatures. l It was this specific process that identified the need to revise the closure status of this action item. Boston Edison management does not consider the action to place in use a draft of a technical specification change process procedure sufficient to consider an item complete. O
E . L, i l l-8 CHANGE TO MANAGEMENT MEETING 86-41, 6 MAY 1987 STATUS LETTER
SUMMARY
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This. change clarifles the earlier reported status of a Technical Sp' edification change preparation checklist. I ORIGINAL COMMITMENT / STATUS: Action
" Develop checklist defining criteria for Technical Specification changes" l Status
" Completed. A checklist has been issued which defines the criteria for preparing Technical Specification change requests.
This checklist was developed using the NRC Draft Policy Statement ; i issued February 1987." O
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CHANGE: The status is more precisely reported as follows: "A draft change checklist was placed in use in February 1987. The final ! draft of the change checklist is part of a change process procedure under review for approval. Approval is expected by 20 November 1987. SOURCE OF COMMITMENT / STATUS: Boston Edison letter 87-070 of 6 May 1987 (status report on Management Meeting 86-41) issue 10.A.1. O
I 8 - I' age 2 f n REASON FOR CHANGE: To clarify the status provided on 6 May 1987- concerning the completeness of this action item. The report thTt the action was , completed is not precise. It was made before a clearly defined / acceptable standard for judging the completeness of actions had I been established. The basis for revising this item is identical ) to'that in Commitment Change f7. Current standards in affect for ; closing items in the regulatory commitments appendix (Appendix I
- 10) include precisely worded completeness acceptance criteria, ]
clearly defined supporting documentation requirements, a knowledgeable independent review and two management certification 'l It was this specific process that identified the j signatures. need to revise the closure status of this action item. Boston Edison management does_not consider the action to place in use a draft of a Technical Specification change checklist i sufficient to consider an item complete. i O l l O
I 9 _10 CHANGE TO MANAGEMENT MEETING 86-41. 6 MAY 87 STATUS LETTER SUhMARY: Tb,is change updates the status reported earlier on the readiness for-implementation of a Plant Design Change (PDC). I ORIGINAL COMMITMENT / STATUS: j Action
" Initiate design changes to establish the minimum flow design basis and.the associated hardware changes."
i Status
" Completed. Plant Design Change (PDC) 86-95 was issued on March 10, 1987."
O CHANGE: Update the status as follows: " Plant Design Change (PDC) 86-95 was issued by the Engineering Dapartment on March 27, 1987. It was reviewed by the Operations Review Committee (ORC) .and returned to Engineering for rework. Rework of the PDC by Engineering was completed in late September 1987 and it was resubmitted to ORC before' implementation." SOURCE OF COMMITMENT / STATUS: Boston Edison Letter 87-070 of 6 May 87 (status report on 1 Management Meeting 86-41) issue 3.B.3. 1 REASON FOR CHANGE: ; To provide an updated status of PDC 86-95. The PDC was issued for construction on October 13, 1987. O 3
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'C) CHANGE TO MANAGEMENT MEETING 86-41, 6 MAY 1987 STATUS LETTER
SUMMARY
This change revises the status reported earlier on establishing controls on Measuring and Test Equipment. ORIGINAL COMMITMENT / STATUS: Action
" Establish control of the Measuring and Test Equipment (M&TE)."
Status
" Completed."(The 1 Mar 1987 status report also reported
" Completed" and included additional descriptive controls information not pertinent to this commitment change.)
i CHANGE: Change the status as follows: "In progress. Controls are being developed to place all M&TE under central facility control". SOURCE OF COMMITMENT / STATUS: Boston Edison letter 87-070 of 6 may 87 (status report on Management Meeting 86-41) issue 4.A.4. REASON FOR CHANGE: The issue of control of M&TE was re-examined as a part of the self assessment that led to formulation and implementation of the Material Condition Improvement Action Plan (MCIAP). M&TE was included in the MCIAP. Although at the time of the 6 thought May 1987 to be i l 86-41 status letter M&TE controls were satisfactory, the ongoing review process built into the MCIAP showed that additional controls over M&TE were required. The need for additional actions has been addressed to the cognizant manager. Followup action will be taken to ensure that added controls will correct the weaknesses identified. Added review under the provisions of the MCIAP will continue. U l
11-CHANGE TO MANAGEMENT MEETING 86-41. 6 MAY 87 STATUS LETTER
SUMMARY
- A This change clarifies the status provided earlier en the inspection of certain check valves.
ORIGINAL COMMITMENT / STATUS: Action
" Inspect similar valves" e
Status
" Completed" CHANGE:
p The status 10 more precisely stated as follows: "An engineering a evaluation was completed. No similar valve applications exist, thus no additional _ inspections are necessary". SOURCE OF COMMITMENT / STATUS: Boston Edison letter 87-070 of 6 May 1987 (status report on Management Meeting 86-41) issue 3.B.5 REASON FOR CHANGE: To more precisely describe the action taken. A root cause analysis of the failures that occurred in the check valves identified the cause to be vertical mounting of valves designed for horizontal service. Only . one other valve of the type in question is installed at Pilgrim, and it is mounted in a application. Thus no additonal inspection is horizontal i considered necessary. O' - i i
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'12 0 CHANGE TO MANAGEMENT MEETING 86-41, 6 MAY 1987' STATUS LETTER
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SUMMARY
1 This change revises the commitment completion date for l implementation of longer term corrective actions for containment ]q isolation valve leakage. l i ORIGINAL COMMITMENT / STATUS: Action l
" Determine root cause and make recommendations to correct failures and implement corrective actions for 15 containment isolation valves that failed LLRT." i i
' Status i "On schedule for completion prior to start-up from RFO 7."
CHANGE: Change the status to read: " or:nulation of longer term actions including- any preventive maintenance requirement c will be completed within ninety Gays after completion of r.ne integrated primary containment leek rate test." i SOURCE O'F COMMITMENT / STATUS: Boston Edison letter 87-070 of 6 May 87 (status report on
-Management Meeting 86-41) issue 4.B.1.
REASON FOR CHANGE: To allow for a measured and prudent approach to formulation of longer term corrective actions, particularly those which may involve changing plant conditions for the performance of preventive maintenance tests. The longer term corrective actions 1 will be based in part on integrated primary containment leak rate l test results and details of the failure root cause analyses. All L= valves will be repaired and the root cause analyses will be [, completed for all valves prior to startup.
13 (D v CHANGE TO MANAGEMENT MEETING 86-41, 6 MAY 87 STATUS LETTER
SUMMARY
This- change clarifies the wording of the commitment for i implementation of corrective action' to address root causes of weld failures. ORIGINAL COMMITMENT / STATUS: Action
" Implement corrective actions to address root causes."
status i
" Schedule for completion prior to startup from RFO 7."
CHANGE: I Change the commitment- as follows: "The root cause analyses are complete. The schedule for implementation of actions to address root causes will be completed prior to startup from RFO 7." SOURCE OF COMMITMENT / STATUS: Boston Edison letter 87-070 of 6 May 1987 (status report on Management Meeting 86-41) issue 3.B.4. l I REASON FOR CHANGE: To clarify the wording of the commitment. Some corrective measures resulting from the root cause analysis are long term and will not ' be completed before startup. All identified cracked welds have been repaired. _L___. . _ . . _ _ _ - . . . _ . -
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i 24 CHANGE TO MANAGEMENT MEETING 86-41, 6 MAY 87 FTATUS LETTER -
SUMMARY
This change. updates the status reported earlier on the readiness 4 for implementation'of a Plant Design Change (PDC). 1 ORIGINAL COMMITMENT / STATUS: Action
" Evaluate tM safety significance of the specific application in l safety-related functions."
Status 1 l
" Complete and report issued.on April 12, 1987."
CHANGE: Update the. status as-follows: "Completad and a revised report
' was issued on 23 September 1987."
! ~ SOURCE OF COMMITMENT / STATUS:
Boston Edison Imtter 87-070 of 6 May 87' (status report on Management Meeting 86-41). Issue 3.B.17. REASON FOR CHANGE: The safety-related HGA relay list (PDC 87-27) was issued as stated on April 12, 1987. Subsequent review identified two more relay applications that had not been included because' they were shown on design drawings as not using the contacts of concern. Field verification showed the contacts of concern to report to Quality be in use. was l A Potential Condition Adverse (PCAQ) issued, (87-129). These two relays have been replaced along with l the original 15 relays identified in the PDC. A detailed walkdown of use of the subject relays was started on 9/28/87 to ensure no further HGA relay problems exist concerning this issue. A walkdown of those HGA relays required for fuel reload was completed before commencing fuel load. Boston Edison 1 Engineering Department will review and approve the complete
.d walkdown report before closing PCAQ 87-129.
15 O CHANGE TO MANAGEMENT MEETING 86-41, 1 MAR & 6 MAY 87 STATUS LETTERS
SUMMARY
i l Tliis change revises- the management level to which - Radiological I Occurrence Reports (RORs) are assigned for tracking of corrective ' j
' action.
l I l] ORIGINAL COMMITMENT / STATUS: Action "RORs to . be transmitted and assigned where possible to Section l Manager level or above." Status I
" Completed February 1986." {
O CHANGE:
. Change the ACTION to read " Group Imader" where "Section Manager" appears.
SOURCE OE COMMITMENT / STATUS: Boston Edison Letters 87-039 of 1 MAR 1987 and 87-070 of 6 May 1987 (stetus reports on Management Meeting 86-41) issue 2.A.1 REASON FOR CHANGE: Accountability for ROR corrective action was initially assigned to the wrong level in the organization. Subsequent to 6 May 1047, it was determined by the Station Manager and concurred in by Senior Management, that the Group Imaders were the best managers to be held accountable for ROR corrective actions and , their effectiveness. RORs are now being assigned to and are j being properly handled by the Group Leaders. Section Managers l are informed of repetitive problems on a case basis and are kept I
.O informed of trends using the monthly ROR report.
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16 CHANGI' TO MANAGEMENT MEETING 86-41 1 MAR 87 AND 6 MAY 87 STATUS LETI'ERS
SUMMARY
TSis change updates a commitment date for making circuit breaker
-maintenance manual changes.
ORIGINAL COMMITMENT / STATUS: Action
" Update breaker maintenance manual to define use of special lubricants and enhance steps for making breaker adjustments."
Status 1 MAR 87: "This effort is in progress. -GE is preparing the manual, and is expected to be complete in April 1987." 6 MAY 87: "On schedule for April 1987." CHANGE: The 6 May 1987 status is updated as follows: "An updated maintenance manual / procedure will be on hand before RFO 8." I SOURCE OF COMMITMENT / STATUS: l Boston Edison letters 87-039 of 1 MAR 87 and 87-070 of 6 MAY 87 (status reports of Management Meeting 86-41) issue 3.B.1. O i L:__ -_- _ l
16 - Page 2 REASON FOR CHANGE: To update the 6 May 1987 status. A test procedure was received in March 1987 which purportedly met the2 needs for breaker adjustments. Review of this procedure subnequent to the 6 May 1987 status letter, rejected the pr'ocedure as inadequate. A GE letter dated 21 August 1987 l forwarded a revised procedure for this breaker work which also
' has been evaluated as inadequate and has been rejected. Boston Edison is pursuing this issue with GE and plans to have an adequate manual / procedure in hand before RFO 8. In the interim, GE will continue to perform the breaker work intended to be covered by that manual / procedure.
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17 CHANGE TO MANAGEMENT MEETING 86-41. 1 MAR 87 STATUS LETTER i
SUMMARY
This change corrects the status provided earlier which incorrectly indicated' that a piece of test piping had been
, installed in the SSW system.
ORIGINAL COMMITMENT / STATUS: ,
- e. , -l Action
" Identify improved materials for SSW service."
w, . . M- Status ,
"In process. Test piping installed. Other tests and experience- ,I . -
of other plants being investigated. This includes consideration I of other materials such as aluminum bronze, titanium, copper nickel and others.'" O-CHANGE: 4 Change status by deleting: " Test piping installed." a q l SOURCE OF COMMITMENT / STATUS: Boston Edison Letter 87-039 of 1 MAR 1987 (status of Management Meeting 86-41) issue 3.B.8. REASON FOR CHANGE: ! The status of the piece of test piping was reported in error. The test piece was at the station but had not been installed. .. ' The test piping piece has now been installed. The regulatory correspondence review practices in effect at the time of submittal of the 1 Mar 1987 status report were not as ! rigorous as present practices to ensure that the correct person was providing status included in correspondence. !
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17 - Page 2 New licensing submittal practices have been implemented to ensure accurate information reporting. Copies of submittals are ! specifically checked to assure the appropriate person is assigned responsibility for verification of statements and status.- An Input Verification Sheet is attached and that individual signs ; that the portions for which he is responsible are correct.- TheA summary cover sheet is then attached to the submittal. cognizant manager certifies that on the cover sheet all portions for which he and his subordinates are responsible have been .., reviewed and the appropriate person has verified the contained l information. , l i O . l l 1 O l l
18 O CHANGE TO MANAGEMENT' MEETING 86-41. 6 MAY 87 STATUS TETTER
SUMMARY
- This change revises completion status provided earlier regarding j an evaluation of replacement of metal links with fuses.
ORIGINAL COMMITMENT / STATUS: Action
" Perform . an engineering evaluation to replace metal links with fuses in motor control circuits" Status
" Comp 1eted" CHANGE:
Change status to read as follows:
" Completed those associated with Appendix R and safety related non-Appendix R equipment. Other non-safety related work will be O completed after startup." -
SOURCE OF COMMITMENT / STATUS: Boston Edison Letter 87-070 of 6 May 1987 (status report on Management Meeting 86-41) issue 3.B.16. REASON FOR CHANGE: This action item, as originally defined within Engineering, was broken into three parts: Appendix R, safety related and other non-safety related equipment. The completed report applied only ! to the first two categories. Some of the non-safety.' related evaluation work is ongoing and not required for startup. Upon completion of power ascension, this item will be scheduled for completion within ninety days. Completion of non-safety related evaluation This work,work although highly can only be desirable, is not a startup prerequisite. i. completed prior to startup at the expense of other work that is required for startup. O i
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. /i CHANGE TO MANAGEMENT MEETING 86-41, 6 MAY 87 STATUS LETTER (f .
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SUMMARY
This change clarifies the . status provided earlier which stated the EAL lesson plans.had been revised. ORIGINAL COMMITM'6NT/ STATUS:
,e ,
'4 Action.,' []' i
" Revise lesson Iplans and conduct operator training for redised procedures." g )'-
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" Lesson plans '.have been revised to incorporate the changes to -
procedures. Operator training was com13eted March 30, 1987." ,
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The. status is more precisely stated as follows: "No lesson \ plarg j revision was necessary as the EAL procedure are used lyi' ^1 lieu of i % J a lesson plan." {
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s i SOURCE OF COMMITMENT / STATUS: f Boston Edis j iAtter 87-070 of 6 May 1987 (status report ont Managehsnt N 9 ting 86-41) issuc S.A.1. i
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REASON FOR CHANGE: s No traditional lesson plans for EAL training are used by Boston j Edison. Rather, actual EAL procedures are used in place of i lesson plans for EAL training. l .
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'J, < CHANGE TO LER 86-014-00
SUMMARY
)
This change clarifies . a prior statement that a new procedure had ' )
'been written. j l
ORIGINAL COMMITMENT / STATUS: Under Corrective' Action: "A new procedure was developed to test j the' subject wiring.. Utilizing the new procedure, the wiring will-
.be tested prior to restart from the current outage."
-[ Note - Reference,is made to a "new procedure" in other places in ~
The. Corrective Action section is the most definitive.] the LER. l CHANGE:
; q /N U 1- . The . status :is more . precisely stated as follows: " Revised the m ' surveillance procedure which -addresses the requirements of.
Technicall Specification 4.5.D.1.a. Review and approval of the procedure revisions romains." t
? SOURCE OF COMMITMENT / STATUS:
LER 86-014-00 .; i REASON:FOR' CHANGE: The choico . of the words "new procedure" in the LER was not precise. An ' extensive revision to' an existing procedure, including new testing methodology, was written to address the testing issue. The extent of the revision constitutes virtually a l ' new procedure, but the revision is to be issued under the existing procedure number. , i r O-
l - 21 q () CHANGE TO MINUTES OF MANAGEMENT MEETINGS 86-22 AND 86-32
SUMMARY
- j This change revises a commitment for replacement of specific RHR system valves during the current outage.
i ORIGINAL COMMITMENT / STATUS: 1 86-22 "The licensee stated that the RHR injection gate valves j (29A and B) would be replaced during the next refueling ; outage." j l 86-32 "The licensee stated that at least two of the system j injection valves, i.e., the MO-1001-29A and B valves, ) will be replaced during this outage." -l I CHANGE: ) 1 m The commitment should be changed as follows: "RHR injection gate i V valve MO-1001-29B will be replaced during this outage; RHR l injection gate valve MO-1001-29A will be evaluated for replacement based on RFO-8 LLRT test results". l SOURCE OF COMMITMENT / STATUS: Management Meeting 86-22 Minutes Management Meeting 86-32 Minutes REASON FOR CHANGE: The condition of valve MO-1001-29A was re-evaluated. Included in this evaluation were the results of LLRTs which showed satisfactory leakage performance, the results of MOVATS testing which showed acceptable time check and torque values and the maintenance history of the valve which showed minimal maintenance requirements. Based on the results of this re-evaluation, it was l determined that it was appropriate to reschedule replacement of the valve based on future LLRT results. O
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'(p, , CHANGE TO MINUTES OF MANAGEMENT MEETING 86-22
SUMMARY
This' change revises a commitment to . hold QA and Station Manager daily meetings. i
- ORIGINAL COMMITMENT / STATUS:
"Also daily meetings between - the Plant Manager and QA will- be
' held to discuss current problems."
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CHANGE: Change " daily".'in the above commitment to read " weekly". L l - SOURCE OF COMMITMENT / STATUS: Management Meeting 86-22 Minutes i L.,- REASON FOR CHANGE: Daily mee. tings proved . to be unnecessary, In Boston Edison's ! response to SALP 86-99, (Boston Edison letter 87-83 of 22 May 4 2 1987), a commitment to hold weekly meetings was reported and is being carried out. These planned meetings are supplemented when necessary by prompt meetings to deal with emerging QA issues. I 1 O- .
l 23 CHANGE TO GENERIC LETTER 87-06 RESPONSE .{ l i
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SUMMARY
I for submission of supplemental data to )
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- ' ' This ' change provides Boston Edison's response to Generic Letter 87-06. l l' q ORIGINAL COMMITMENT / STATUS
Boston -- Edison letter 87-103 of 11 June 1987 which provided the response to Generic' Letter 87-06. CHANGE: Boston Edison will submit another letter containing supplemental' information by 15 December 1987, identifying additional pressure isolation valves called for by Generic Letter 87-06. I SOURCE OF CCMMITMENT/ STATUS: Boston Edison letter 87-103 of 11 June 1986:
.r REASON FOR CHANGE:
Continuing review of the data showed additional- valves which should have been included in the list provided. The review will be completed'and a final list submitted by 15 December 1987.
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24 CHANGE TO MANAGEMENT MEETING 86-41. 1 MAR 87 AND 6 MAY 87
SUMMARY
This change clarifies the commitment to identify all the uses of metal links in motor control circuits before startup. ORIGINAL COMMITMENT / STATUS: Action
" Determine where links are used in motor control circuits."
Status "Both the 1 Mar 87 and 6 May 87 status letters indicated that this work was scheduled for completion before startup from RFO-7. CHANGE: . The status is more precisely stated to indicate that metal links only in Appendix R and safety related motor control circuits will O he ide tified defore startue from Rro-7. SOURCE OF COMMITMENT / STATUS: Boston Edison letters 87-039 of 1 Mar 87 and 87-070 of 6 May 87 (status reports on Management Meeting 86-41) issue 3.B.16. REASON FOR CHANGE: This action item covers the same equipment and is closely related to the item revised in Commitment Change Number 18. The work as defined within Engineering is broken down into three categories: Appendix R, safety related and other non-safety related equipment. The commitment to complete identification work before startup applied only to the first two categories. Other non-safety related work will be completed within five months of Restart. Actual replacement work and drawing revisions will follow the completion of identification and evaluation work. O
.. 25; CHANGE TO MANAGEMENT MEETING 86-41,'l MAR 87 STATUS LETTER
SUMMARY
;This change; revises the commitment for vice presidents to issue reprimands on. late deficiency report responses.
ORIGINAL. COMMITMENT / STATUS: Action.
" Reinforce executive management support and commitment to ' the Quality Assurance Program."
Status
" completed.- Vice presidents will issue written reprimands to department managers who fail to meet deficiency report commitments."
CHANGE: ( The status should be changed to show that the Vice President for Engineering and QA will continue to issue reprimands and that the q Station Manager will' issue reprimands to his subordinates at the ' station'in lieu of the Vice President-Nuclear Operations. SOURCE OF COMMITMENT / STATUS: Boston Edison letters 87-039 of 1 Mar 87 (status reports on Management Meeting 86-41) issue 3.A.1. ! REASON FOR CHANGE: The duties of the Vice President-Nuclear Operations have been ! temporarily assumed by the Senior Vice President-Nuclear. The i Senior Vice President-Nuclear has delegated the authority for issuing reprimands concerning DRs to the Station Manager for those managers reporting to the Station Manager. , l
APPENDIX 12 SYSTEM
SUMMARY
STATUS REPORT
- 1. The purpose of this appendix is to provide informa' tion on
.The System Status Milestone Review process, and prior to j restart the status and review results for'each system listed i in Table A12-1. l
- 2. System Specialists are assigned responsibilities for tracking work on specific systems, and carry out the following functions:
A. Review outstanding work items in applicable work tracking systems to identify for each system listed in Table A12-1, the required work scope (both hardware and software). B. Maintain the status of work progress in a System Status Book.
- c. Maintain the status of significant outstanding testing requirements for inclusion in a System Status Book.
D. Provide pc-lodic summary status reports for management.
- 3. System Status Books are maintained for each of the systems listed in Table A12-1 (attached). The information in the system books includes walkdown reports, modification status updates, outage schedules and other pertinent information.
These status books are available at the station for review.
- 4. In accordance with. Volume 1 of the Restart Plan, the revision of Volume 2 updated just prior to requesting restart will include the following information for each system listed in Table A12-1:
A. Major projects and improvements accomplished. B. Significant issues identified and resolved.
- c. Summary of remaining action items specifically scheduled in the approach to startup.
D. Summary of significant testing results. O
TABLE'A12-1 4 Cyat=1 St2tu3 R vicwa R0 a Functicn of Plant Mil @2tenn Milestone. Plant System Reload Hydro ILRT Critical Main Steam X X X-
~ Reactor Recirculation X. .X- X X
' Control' Rod Drives y X X X Sampling X 'X X- X Feedwater X X X
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- Turbine: Steam Bypass X 1
.Offgas/ Augmented Offgas X
. Primary Cont . Atmos. Control
. X X-Residual Heat Removal X X- X X Reactor Standby Liquid Control X X X X l Reactor Water Cleanup X X X X !
. Reactor Core Isol Cooling 'X X X j' Core Spray X. X X X Gland Seal X Extraction Steam .X Heater' Drains & Vents X Condensate X X Fuel Pool Cooling X Demineralized Water X X. X X l High Pressure Coolant Inject. X X X -l Heating Ventilating & Air Cond. X X X X {
condensate Vent & Drain X' I Condensate Transfer X X l Circulating Water X X l [ X Screen Wash i Service Water X X X X Closed Cooling Water X X X X ! Instrument-Air X X X X 1 Service' Air X X X X i Turbine Lube Oil X Diesel Generator Fuel X X X X j Communications X X ; Instrumentation & Control X X X X l Power Systems X X X X I Standby Gas Treatment X X X X j Fuel Handling & Storage X ! Containment & Reactor X X X X i X I Turbine Generator & Aux. Condenser & Condenser Aux. X X i Reactor Vessel & Aux. X X X X Diesel Gen. & Aux. X X X X Hydrogen Water Chemistry X ] d NOTES:
- X indicates comprehensive update / review required to enter l each milestone. ]
- The " Hydro" column identifies those systems required for a !
Class I Hydro. LO ) _}}