ML20058N401
| ML20058N401 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 12/13/1993 |
| From: | Collins S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Milhoan J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| NUDOCS 9312210380 | |
| Download: ML20058N401 (41) | |
Text
.
UNtTED STATES f[gpa REC
?g NUCLEAR REGULATORY COMMISSION
[
REGION IV
[
611 RYAN PLAZA DRIVE, SUITE 400 o,
AR LINGTON, T E XAS 76011-8064 DEC 131993 MEMORANDUM FOR: James L. Milhoan, Regional Administrator L. Joseph Callan, Acting Associate Director for Projects Office of Nuclear Reactor Regulation FROM:
Samuel J. Collins, Director, Division of Reactor Safety and STP Restart Panel Chairman
SUBJECT:
SOUTH TEXAS PROJECT RESTART ACTION PLAN, REVISION 1 Attached for your information is Revision 1 of the South Texas Project Restart Action Plan. As noted in the cover memorandum for Revision 0, the Restart Action Plan status will be updated and issued approximately monthly by the Panel. Minor revisions may be made without seeking your approval, but approval will be requested for any significant revisions.
f a$e lhector Division of Reactor Safety and STP Restart Panel Chairman
Enclosure:
South Texas Project Restart Action Plan - Revision 1 9312210380 931213 0s l! \\
PDR ADOCK 05000498 I
P PDR E;
's James L. Milhoan ;
i l
cc w/ enclosure:
Houston Lighting & Power Company
-ATTN: James J. Sheppard, General Manager Nuclear Licensing P.O. Box 289 Wadsworth, Texas 77483 City of Austin Electric Utility Department ATTN:
J. C. Lanier/M. B. Lee 721 Barton Springs Road Austin, Texas 78704 City Public Service Board l
ATTN:
K. J. Fiedler/M. T. Hardt P.O. Box 1771 San Antonio, Texas 78296 i
Newman & Holtzinger, P. C.
ATTN: Jack R. Newman, Esq.
1615 L Street, NW Washington, D.C.
20036 1
Central Power and Light Company ATTN:
G. E. Vaughn/T. M. Puckett P.O. Box 2121 Corpus Christi, Texas 78403 I
INPO Records Center 700 Galleria Parkway l
Atlanta, Georgia 30339-5957 l
Mr. Joseph M. Hendrie 50 Bellport Lane Bellport, New York 11713 Bureau of Radiation Control State of Texas 1100 West 49th Street Austin, Texas 78756 Judge, Matagorda County Matagorda County Courthouse 1700 Seventh Street Bay City, Texas 77414
- James L. Milhoan -;
I l
Licensing Representative Houston Lighting & Power Company.
l Suite 610
[
Three Metro Center i
Bethesda, Maryland 20814 i
2 r
Houston Lighting & Power Company ATTN:
Rufus S. Scott, Associate l
General Counsel P.O. Box 61867 t
Houston, Texas 77208 i
Houston Lighting & Power Company ATTN: William T. Cottle, Group i
Vice President, Nuclear P.O. Box 289 2
Wadsworth, Texas 77483 i
t I
l t
3 f
i 1
J J
I DEC j 31993 James L. Milhoan bcc w/ enclosure:
DMB (IE01) 'RIV J. Callan, NRR (12G18) T. Murley, NRR(12G18)
J. Milhoan, S. Collins, RIV A. B. Beach, RIV E. Adensam, NRR(13E4)
W. Johnson, RIV W. Russell, NRR (12G18) J. Roe, NRR (13E4 )
D. Loveless, SRI, RIV L. Kokajko, NRR(13E16) S. Black, NRR (13H15)
D. Chamberlain, RIV A. Howell, RIV J. Montgomery, RI(V9AI)
E. Imbro, NRR (9A1)
P. Koltay, NRR(9A1)
J. Jacobson, NRR A. Thadani, NRR (8E2)
B. Boger, NRR (10H5)
C. Rossi, NRR (9A2)
F. Congel, NRR (10E2)
J. Wiggins, NRR (RI)
C. Hackney, RIV J. Gilliland, RIV M. Satorius, RIV T. McKernon, RIV T. Westerman, RIV D. Powers, RIV J. Pellet, RIV L. Constable, RIV I. Barnes, RIV B. Murray, RIV C. Sudman 3
l RIV:C:DRP/A*
- NRR:PM*
NRR:PD*
D:DRSS*
WDJohnson DPloveless LEKokajko SCBlack DChamberl ain 12/ /93 12/ /93 12/ /93 12/ /93 12/ /93 DD:DRS*
D:DRP*
D:DRS('O ATHowell ABBeach SJ6ol'l k f'
12/ /93 12/ /93 12/6/93/
i
- Previously concurred
'l' 200005
James L. Hilhoan DEC l 3 lgm bec w/ enclosure:
~
DMB (IE01)
J. Milhoan, RIV J. Callan, NRR (12G18) T. Murley, NRR(12G18)
S. Collins, RIV A. B. Beach, RIV E. Adensam, NRR(13E4 )
l W. Johnson, RIV W. Russell, NRR(12G18) J. Roe, NRR (13E4)
D. Loveless, SRI, RIV L. Kokajko, NRR(13E16) S. Black, NRR (13H15) l D. Chamberlain, RIV A. Howell, RIV J. !4ontgomery, RIV E. Imbro, NRR (9 A1)
P. Koltay, NRR(9 A1)
J. Jacobson, NRR (9 A1)
A. Thadani, NRR (8E2)
- 8. Boger, NRR (10H5)
C. Rossi, NRR (9A2) i F. Congel, NRR (10E2) J. Wiggins, NRR (RI)
C. Hackney, RIV J. Gilliland, RIV-M. Satorius, RIV T. McKernon, RIY T. Westerman, RIV D. Powers, RIV J. Pellet, RIV L. Constable, RIV I. Barnes, RIV B. Murray, RIV i
C. Sudman I
RIV:C:DRP/A*
- NRR:PM*
NRR:PD*
D:DRSS*
WDJohnson DPloveless LEKokajko SCBlack DChamberlain 12/ /93 12/ /93 12/ /93 12/ /93 12/ /93
)
DD:DRS*
D:DRP*
D:DRS ( l ATHowell ABBeach SJCol'l Y
/
12/ /93 12/ /93 12/\\h/93
)
- Previously concurred
i 1
SOUTH TEXAS PROJECT RESTART ACTION PLAN - REVISION 1 A.
GENERAL..............................
I A.1 PURPOSE...........................
1 i
1 A.2 OBJECTIVES.........................
1 A.3 BACKGROUND.........................
A.4 RESTART ACTION PLAN OVERVIEW 3
B.
PROCESS..............................
5 B.1 INITIAL NRC RESPONSE 5
B.2 NOTIFICATIONS......................._.
6 i
B.3 ESTABLISH AND ORGANIZE THE NRC REVIEW PROCESS........
7 B.4 REVIEW IMPLEMENTATION....................
9 B.5 RESTART AUTHORIZATION....................
13 B.6 RESTART AUTHORIZATION NOTIFICATION 14 15 C.
ISSUES..............................
C.1 ASSESSMENT OF ROOT CAUSE IDENTIFICATION AND CORRECTION 15 i
C.2 ASSESSMENT OF LICENSEE MANAGEMENT..............
18 l
C.3 ASSESSMENT OF PLANT AND CORPORATE STAFF...........
22 C.4 ASSESSMENT OF PHYSICAL READINESS OF THE PLANTu.
26 C.5 ASSESSMENT OF COMPLIANCE WITH REGULATORY REQUIREMENTS....
28 C.6 C0 ORDINATION WITH INTERESTED AGENCIES / PARTIES........
29 D.
PLANT SPECIFIC STARTUP ISSUES...................
30 l
E.
RESTART INSPECTIONS........................
35 l
l l
l
l A.
GENERAL A.1 PURPOSE l
To provide a basis to plan and coordinate NRC review activities for restart of I
the South Texas Project units.
A.2 OBJECTIVES j
To ensure that NRC review efforts are consistently developed and implemented, specific guidance is provided to support:
l a.
Determining restart issues for review, 1
\\
b.
Identification of the basic tasks needed to review and approve plant restart, and l
c.
Coordination and tracking cf restart review activities.
A.3 BACKGROUND Both units at STP were shut down in early February 1993. They have remained l
shut down as a result of numerous broad problems identified by the NRC and the licensee.
j On February 3, 1993, following a reactor trip, the Unit 2 turbine-driven
]
auxiliary feedwater pump started and immediately tripped on overspeed. On February 4,1993, Unit 1 was required to shut down as a result of repeated j
l failures of the turbine-driven auxiliary feedwater pump to start on demand and operate without tripping on overspeed. As a result of these turbine-driven auxiliary feedwater pump problems, NRC issued a Confirmatory Action Letter (CAL) to the Houston Lighting and Power (HL&P) Company on February 5, 1993, and dispatched an augmented inspection team (AIT) to investigate the details surrounding the turbine-driven auxiliary feedwater pump problems. The CAL, and its two supplements, identified a number of issues which required resolution prior to either unit being restarted.
The NRC Region IV Regional Administrator chartered the STP Review Panel on March 11, 1993. The purpose of the STP Review Panel is to:
- Assure consistent approach to issues being identified at South Texas Project and attempt to reach an agency consensus and united approach to addressing the problems at South Texas Project.
- Assure that the followup on safety significant issues is being properly coordinated and scheduled.
- Schedule significant meetings and inspections.
- Assure that the views and concerns of different NRC offices are properly addressed.
- Assure proper coordination for the followup of issues that are identified by the Diagnostic Evaluation Team (DET) inspection.
1
... i
I On April 12, 1993, it was determined that NRC Inspection Manual Chapter 0350,
" Staff Guidelines for Restart Approval," was applicable for the South Texas Project Electric Generating Station (STP) because of its extended shutdown and previous indications of serious deficiencies in licensee management effectiveness. The STP Review Panel assumed the role and responsibilities of the STP Restart Panel. These responsibilities include-1.
Reviewing available information related to the plant shutdown 2.
Developing the Restart Action Plan 3.
Reviewing the licensee's corrective action or improvement program and ensuring that it addresses identified problems and weaknesses 4.
Maintaining an ongoing overview of licensee performance 5.
Conducting periodic meetings with the licensee to discuss progress toward satisfactory completion of the program 6.
Providing oversight and coordination of the NRC's followup activities, reviewing inspection plans and findings, and reviewing licensee performance; identifying areas where NRC inspection and technical review are needed 7.
Providing periodic assessments of licensee performance and corrective actions to NRC management 8.
Providing a recommendation to the Regional Administrator and the Director of NRR for approval of restart after satisfactory completion of the licensee's restart program In addition to the AIT activities, several special inspections have been conducted since February 1993, in response to compliance and regulatory issues at STP. Several of these inspections resulted in enforcement action being taken. Corrective actions have been proposed by the licensee.
Additionally, the NRC Office for Analysis and Evaluation of Operational Data conducted a diagnostic evaluation of the STP during the period March 29 to April 30, 1993. The findings of this effort were forwarded to the licensee on June 10, 1993. Numerous items were documented in this report, including a number of issues that NRC considered of sufficient scope and safety significance to require resolution prior to either unit being restarted.
In initial response to the Diagnostic Evaluation Team (DET) report, the licensee submitted a letter on August 5,1993, and forwarded their Operational Readiness Plan (ORP) on August 28, 1993.
In addition to responding to the DET short-term problems that the licensee considered necessary to resolve prior to restart, the ORP addressed the planned actions in response to the CAL, special and routine Regional inspections, and other identified concerns and problems.
l The ORP addressed initiatives that the licensee considered necessary to be completed prior to the resumption of power operation on either unit. The licensee's Business Plan was scheduled to be issued on October 15, 1993.
It i
will describe the initiatives being undertaken to effect sustained performance improvements at the site.
g Rev 1 i
A.4 RESTART ACTION PLAN CVERVIEW A comprehensive NRC review of the restart process is required. The plants are in a safe shutdown condition and measures are in place to physically maintain the plants in a safe shutdown condition.
This Restart Action Plan is intended to include expected NRC actions that will be required to be taken before restart of the STP units, including those actions not directly related to the initiating event. The plan defines:
the actions which must be accomplished by the NRC, as a minimum, to approve restart; which organization has the lead responsibility for each action; which plant specific issues must be resolved before restart; and who has the actual responsibility for restart approval.
The Panel retains responsibility for assessment of the issue and determining whether the issue has been satisfactorily addressed. The STP Restart Panel will make updates and minor revisions to the Restart Action Plan without seeking approval from the Regional Administrator and the Associate Director for Projects.
Revisions which are determined by the Panel to be significant will be submitted for approval.
Section B, " PROCESS," of this plan provides generic tasks that support the Restart Action Plan.
This section outlines the overall review process needed for the NRC to authorize restart of the facility.
Section C, " ISSUES,' contains issues for consideration and areas requiring assessment during the restart review.
The issues in this section are broader than the plant specific restart issues and have been determined to be applicable because of the declining performance of the licensee and the extended length of the shutdown.
It will not be necessary for each item on the checklists to be assessed, but enough items on a checklist must be reviewed to assess the broader areas such as management oversight and effectiveness.
Section D, " PLANT SPECIFIC STARTUP ISSUES," lists plant-specific issues which must be evaluated and resolved prior to plant startup. This list was developed from a review of the Diagnostic Evaluation Team Report, the Executive Director for Operations staff actions memorandum following the Diagnostic Evaluation, the Confirmatory Action Letter and its supplements, the licensee's Operational Readiness Plan, the allegation review process, and routine and special NRC reports, including the Augmented Inspection. Criteria for selection of restart issues ensured inclusion of issues whose resolution is required to: ensure safe facility operation; comply with Technical Specification and other regulatory requirements; satisfy the plant's design and licensing basis; ensure effective management oversight; or ensure an effective corrective action process.
Each of the restart issues is, or will be, included on the licensee's restart issue list.
Prior to restarting either STP unit, the licensee will resolve each restart issue to its satisfaction and to the NRC's satisfaction. The licensee will provide a briefing for the NRC staff on the readiness for plant restart, including the issues included in the Confirmatory Action Letter and its supplements prior to restart.
This meeting will be open to public observation.
Section E, " RESTART INSPECTIONS," lists the inspections to be completed to evaluate the licensee's response to the startup issues.
Issues listed in Sections C and D will be assessed or inspected by resident inspectors, regional inspectors, or an Operations Readiness Assessment Team.
In addition, some areas or items may be assessed by the STP Restart Panel.
3
.. 3
Each of the checklists in Sections B and C include columns to record the NRC organization with lead responsibility for the item and the date the item was closed. The list in Section D includes a column.to record the date the issue was closed. The reference /information notes following each checklist table will document the detailed status of each item,~ including reference to closecut documentation.
The STP Restart Panel is responsible for implementation of the STP Restart Action Plan. The STP Restart Panel will maintain and periodically review the Restart Action Plan. These actions should:
(1) determine review status, (2) verify necessary tasks and items are complete for each phase of the review, and (3) ensure that review tasks and issues for assessment remain consistent with the known facts and status of the restart effort. The generic lists in Sections B and C should be reviewed when significant milestones are completed and prior to restart authorization to ensure any emerging items are considered.
Eev 1
..m-.
B.
PROCESS B.1 INITIAL NRC RESPONSE:
j This section outlines the general NRC restart review process. The major process steps (i.e., Initial Response, Initial Notifications, etc.) are broken down into potential tasks that are provided in a checklist format. The short discussion before each major process step provides insight into the intended activity. An effort was made to place the major steps and tasks in the general order of performance; however, the exact sequence of events cannot be l
predicted in advance. Thus, many of the major process steps and the specific tasks are expected to be performed in parallel.
j The tables provide a column to indicate the lead responsible organization and l
closeout date. Tasks which the restart panel has determined to not be applicable to the STP restart process are marked "NA."
l l
f TASK RESP ORG DATE CLOSED a.
Initial notification and NRC management RIV 02/04/93 discussion of known facts and issues i
b.
Identify / implement additional inspections RIV 02/04/93 (i.e., AIT, IIT, or Special) c.
Determine' need for formal regulatory RIV 02/05/93 l
response (i.e., Order or CAL) j a
d.
Determine need for senior management RIV, NRR 03/11/93 involvement e.
Identify other parties involved, i.e.,
RIV, NRR 02/25/93 NRC Organizations, other Federal agencies, and industry organizations j
Reference /Information B.I.a PN 4-93-003 B.I.b PN 4-93-003; AIT dispatched. AIT Inspection Report 9307 issued on l
03/24/93.
B.I.c PN 4-93-003; CAL 4-93-04 issued
{
B.I.d STP Review Panel Charter approved B.I.e AEOD was the only other organization involved in the short-term response.
l t
5
- ~ 2
i B.2 NOTIFICATIONS:
Initial notification of the event quickly communicates NRC's understanding of the event and its immediate response to the parties having an interest in the d
event. Notification to regional and headquarters offices of cognizant Federal agencies may be appropriate. As the review process continues, additional and continuing notifications may be required.
TASK RESP ORG DATE CLOSED a.
Issue Daily and Directors Highlight NRR Ongoing b.
Issue PN RIV 02/04/93 c.
Conduct Commissioner Assistants' RIV 06/25/93 Briefing d.
Issue Commission Paper NA NA Cognizant Federal agencies notified NA NA e.
(i.e., FEMA, EPA, D0J, DOL) f.
State and Local Officials notified RIV Ongoing g.
Congressional notification NA NA Reference /Information B.2.a Directors Highlight 02/17/93 and approximately weekly thereafter B.2.b PN 4-93-003 B.2.c Conducted in conjunction with the Commission briefing on the results of the June 93 senior managers meeting.
B.2.d NA B.2.e NA B.2.f Monthly public meeting announcements.
The Deputy Regional Administrator and the STP Restart Panel Chairman briefed the Texas Public Utility Commission and the Austin City Council on 09/09/93.
B.2 9 PN 4-93-003. NRR discussed with Congressional Affairs.
6
l
~
i B.3 ESTABLISH AND ORGANIZE THE NRC REVIEW PROCESS:
It will be necessary to establish and organize the NRC restart review to ensure the effective coordination of resources in evaluating the restart i
process. Effective interfaces within and outside the NRC are critical to properly identify, coordinate, and resolve the pertinent issues.
Consider both regional and headquarters offices of cognizant State and Federal agencies.
TASK RESP ORG DATE CLOSED a.
Establish the Restart Panel RIV 03/11/93 l
b.
Assess available information (i.e., inspection PANEL Ongoing I
results, licensee self-assessments, industry reviews) c.
Obtain input from involved parties both within PANEL Ongoing i
NRC and other Federal agencies, such as FEMA, EPA, D0J, D0L d.
Conduct Regional Administrator Briefing PANEL Ongoing e.
Conduct NRR Executive Team Briefing NRR 06/93 f.
Develop the Case Specific Checklist (CSC)
RIV/DRP 10/21/93 9
Develop the Restart Action Plan RIV/DRP 10/21/93 h.
Regional Administrator approves Restart Action RIV 10/21/93 Plan i.
NRR Associate Director and/or NRR Director NRR 10/25/93 approves Restart Action Plan j.
Implement Restart Action Plan PANEL Ongoing k.
Modify CAL /0rder as necessary RIV/DRP 05/07/93 Reference /Information l
B.3.a First Panel meeting held on 02/25/93.
Panel charter approved on 03/11/93.
l B.3.b Panel meeting notes of 02/25/93 B.3.c No external issues identified.
B.3.d Briefings provided following Panel meetings.
B.3.e Full discussion at June 93 Senior Managers Meeting. NRR will provide periodic Executive Team briefings.
B.3.f This document includes the CSC.
B.3 9 This document is the Restart Action Plan.
7 4
m
B.3.h Restart Action Plan approved by Regional Administrator 10/21/93.
B.3.1 Restart Action Plan approved by NRR Associate Director 10/25/93.
B.3.j Restart Action Plan implementation in progress 10/25/93.
B.3.k CAL Supplement issued May 7,1993.
CAL Supplement 2 issued on October 15, 1993.
r l
i i
8
l B.4 REVIEW IMPLEMENTATION:
The review can be accomplished by a variety of methods including inspections, testing, evaluation of licensee self-assessments, evaluation of licensee action plans, and regulatory actions (i.e., Orders, CAL's).
Early establishment of the review areas will assist in defining the methods to i
perform the review. Once the licensee has developed its corrective action plan, the NRC shall review that plan to verify its completeness and adequacy The NRC will also need to determine which corrective actions will be required l
to be implemented before restart and, thus, become restart issues which can be l
deferred to some later date as long-term corrective actions. The discussions and issues provided in Section C of this appendix provide additional information to support the review activities described below.
B.4.1 Root Causes and Corrective Actions:
t TASK RESP ORG DATE CLOSED i
a.
Evaluate findings of AIT, IIT, or Special RIV 03/24/93 i
Team Inspection b.
Licensee performs root cause analysis and PANEL 10/15/93 l
develops corrective action plan for root l
causes c.
NRC evaluates licensee's root cause PANEL 11/18/93 determination and corrective action plan r
Reference /Information B.4.1.a AIT IR 9331, AIT Followup IR 9305 dated 04/08/93.
{
B.4.1.b DET response status letter submitted 08/05/93. Operational Readiness Plan submitted 08/28/93. Business Plan submitted 10/15/93.
l B.4.1.c NRC letters of 08/26/93 and 09/22/93 acknowledged receipt of licensee submittals of 08/05/93 and 08/28/93. NRC letter of 11/18/93 acknowledged receipt of Business Plan.
B.4.2 Assessment of Eauipment Damage:
This section is not applicable for the South Texas Project restart approval.
)
9
.,.__.____m._.,.e
a 9
B.4.3 Determine Restart Issues and Resolution:
The establishment of the restart issues that require resolution before restart demands a clear understanding of the issues and the actions required to address those issues by both the NRC and the licensee. This table outlines steps to determine the restart issues and NRC's evaluation of their resolution.
2 TASK RESP ORG DATE CLOSED l
Review / evaluate licensee generated restart PANEL 10/05/93 a.
issues
)
b.
Independent NRC identification of restart PANEL 09/27/93 I
issues (consider sources external to NRC and licensee) c.
NRC/ licensee agreement on restart issues PANEL 10/15/93 d.
Evaluate licensee's restart issues PANEL Ongoing implementation process e.
Evaluate licensee's implementation PANEL Ongoing verification process Reference /information l
B.4.3.a Public meeting and Panel meeting.
B.4.3.b Panel meeting notes.
IR 9331 B.4.3.c CAL Supplement 2 issued. Lists compared in IR 9333.
3 B.4.3.d Refer to IR 9331 and subsequent reports.
4 B.4.3.e Line management assessment and independent assessment processes l
reviewed in IR 9333.
l I
r s
i a
10 1
...,.,,,...,..n,..n
~. ~. -.. _,,....,_... <.
i B.4.4 Obtain Comments:
Since some shutdowns involve a broad number of issues, solicitation of comments from diverse sources may be appropriate. The decision to solicit comments from a group and the level of participation should be made on a case-by-case basis.
Input from these groups should be factored into the restart 3
process when they contribute positively to the review.
Note:
If needed, comments concerning the adequacy of state and local emergency planning and j
preparedness must be obtained from FEMA headquarters through NRR.
F TASK RESP ORG DATE CLOSED f
a.
Obtain public comments PANEL Ongoing i
b.
Obtain comments from State and Local PANEL Ongoing Officials f
Obtain comments from applicable Federal PANEL /NRR NA c.
agencies l
Reference /Information B.4.4.a DET public exit meeting at site 06/03/93.
Public meetings at site 07/16/93 and 09/08/93.
Public meeting in the RIV office 10/05/93.
t Public meetings at site 10/29/93 and 12/02/93.
B.4.4.b The Deputy Regional Administrator and the STP Restart Panel Chairman briefed the Texas Public Utility Commission and the Austin City Council on 09/09/93. City of Austin representatives met with the Restart Panel Chairman on 11/16/93.
B.4.4.c Not needed for implementation review.
i
'I 11
.., 3
8.4.5 Closecut Actions:
When the actions to resolve the restart issues and significant concerns are 1
substantially complete, closeout actions are needed to verify that planned inspections and verifications are complete. The licensee should certify that i
corrective actions required prior to restart are complete and that the plant is physically ready for restart. This table provides actions associated with i
completion of significant NRC reviews and preparations for restart.
TASK RESP ORG DATE CLOSED a.
Evaluate licensee's restart readiness PANEL Ongoing sel f-assessment b.
NRC evaluation of applicable items from PANEL section C " ISSUES" complete c.
Restart issues closed PANEL d.
Cunduct NRC Restart Readiness Team NRR Inspection e.
Isste Augmented Restart Coverage RIV/DRP Inspection Plan f.
Comnents from other parties considered PANEL g.
Determine that all conditions of the CAL PANEL and its Supplements are satisfied h.
Re-review of Generic Restart Checklist PANEL complete Reference /Information B.4.5.a Discussed in IR 9333.
]
B.4.5.b i
B.4.5.c B.4.5.d B.4.5.e B.4.5.f B.4.5 9 B.4.5.h 12 m.
2
B.5 RESTART AUTHORIZATION:
When the restart review process has reached the point that the issues have been identified, corrected, and reviewed, a restart authorization process is begun. At this point the restart panel should confirm that all actions are substantially complete and that the panel has not overlooked any items.
TASK RESP ORG DATE CLOSED a.
Prepare restart authorization document and RIV/DRP basis for restart b.
NRC Restart Panel approves Restart PANEL Authorization c.
No restart objections from other PANEL applicable H0 offices d.
No restart objections from applicable PANEL Federal agencies e.
Regional Administrator concurs in Restart RIV Authorization f.
NRR Associate Director and/or NRR Director NRR Concurs in Restart Authorization g.
E00 concurs in Restart Authorization RIV h.
Conduct ACRS briefing / notification NRR i.
Conduct Commission briefing / notification NA NA l
j.
Commission concurs in Restart NA NA Authorization k.
Regional Administrator authorizes restart RIV Reference /Information B.5.a B.5.b B.5.c B.S.d B.S.e B.S.f B.5 9 B.5.h Pending need determination.
Preliminary ACRS staff notification made by M. Virgilio to J. Larkins 05/08/93.
B.5.i NA B.S.j NA B.5.k 13
B.6 RESTART AUTHORIZATION NOTIFICATION:
Notify the applicable parties of the restart aL+horization.
Communication of planned actions is important at this stage to ersure that NRC intentions are clearly understood.
TASK RESP ORG DATE CLOSED a.
Commission NRR b.
EDO RIV/NRR c.
Congressional Affairs NRR d.
Applicable Federal Agencies RIV/NRR f.
Public Affairs RIV g.
State and Local Officials RIV Reference /Information B.6.a B.6.b B.6.c B.6.d B.6.e B.6.f B.6.g 14 l
C.
ISSUES C.1 ASSESSMENT OF ROOT CAUSE IDENTIFICATION AND CORRECTION:
C.1.1 ROOT CAUSE ASSESSMENT:
The root cause(s) of the event or the conditions requiring the shutdown should be identified and corrected. A comprehensive licensee corrective action plan should be developed that addresses the root cause(s) and all applicable issues i
including corrective action, implementation, and verification. The corrective action plan should also include sufficient measures to prevent recurrence of problems. The NRC shall review the licensee's corrective action plan to verify its completeness and adequacy and to determine which corrective actions will be required to be implemented before restart and which can be deferred to some later date as long-term corrective actions.
The NRC staff will review the licensee's corrective action activities and use the appropriate tools available in the regulatory program to determine the acceptability of these actions with respect to safe operations. The tools l
which are available include:
staff reviews; the systematic assessment of licenses performance (SALP); inspections, including special team inspections; requests under 10 CFR 50.54(f); senior management meetings; enforcement conferences; and a restart panel. The results of the staff's reviews will be documented by safety evaluations, license amendments, orders, Confirmatory i
l Action Letters, inspection reports, Commission meeting transcripts, and enforcement documents.
j i
ISSUES RESP ORG DATE CLOSED i
l 1.
Conditions requiring the shutdown RIV 02/05/93 are clearly understood 2.
Root causes of the conditions PANEL 06/10/93 requiring the shutdown are clearly understood 3.
Root causes of other significant PANEL 06/10/93 i
problems are clearly understood 4.
Evaluate adequacy of the root cause RIV analysis program NRR/DRIL i
Reference /Ir'ormation 1.
CAL of 02/05/93; CAL Supplements of 05/07/93 and 10/15/93; DET Report of 06/10/93 2.
CAL of 02/05/93; CAL Supplements of 05/07/93 and 10/15/93; DET Report of 06/10/93. TDAFW issues discussed in IR 9338.
3.
CAL of 02/05/93; CAL Supplements of 05/07/93 and 10/15/93; DET Report of 06/10/93 4.
15
,..m.-
.,_+m.n,
I C.I.2 DAMAGE ASSESSMENT:
Not applicable for South Texas Project.
4 C.I.3 CORRECTIVE ACTIONS:
ISSUES RESP ORG DATE CLOSED 1.
Evaluate adequacy of the comprehensive PANEL 11/18/93 corrective action plan 2.
Evaluate adequacy of the corrective RIV Ongoing action programs for specific root NRR/DRIL causes 3.
Assess control of corrective action RIV item tracking NRR/DRIL 4.
Effective corrective actions for the RIV conditions requiring the shutdown have NRR/DRIL been implemented 5.
Effective corrective actions for other RIV significant problems have been NRR/DRIL implemented 6.
Adequacy of the licensee's corrective RIV action verification process NRR/DRIL Reference /Information 1.
DET response status letter submitted 08/05/93.
Operational Readiness Plan submitted 08/28/93. Business Plan submitted 10/15/93. NRC letters of 08/26/93 and 09/22/93 acknowledged receipt of licensee submittals of 08/05/93 and 08/28/93.
NRC letter of 11/18/93 acknowledged receipt of Business Plan.
2.
3.
IR 9333 found that appropriate mechanisms were in place to control SPR backlogs and manage new incoming SPRs.
4.
IR 9338 addressed root causes for TDAFW pump issues.
5.
6.
16
t C.l.4 SELF-ASSESSMENT CAPABILITY:
The occurrence of an event may be indicative of potential weaknesses in the licensee's self-assessment capability. A strong self-assessment capability creates an environment where problems are readily identified, prioritized, and tracked.
Effective corrective actions require problem root cause identification, solutions to correct the cause, and verification methods that ensure the issue is resolved.
Senior licensee management involvement in self-assessment is treated separately.
ISSUES RESP ORG DATE CLOSED 1.
Effectiveness of Quality Assurance Program RIV/DRS 2.
Adequacy of Industry Experience Review RIV/DRS Program 3.
Adequacy of licensee's Independent Review RIV/DRS Groups 4.
Adequacy of deficiency reporting system RIV NRR/DRIL 5.
Staff willingness to raise concerns RIV/DRS 6.
Effectiveness of PRA usage NA NA 7.
Adequacy of Co=ttment Tracking Program NA NA 8.
External audit (i.e., INPO) capability PANEL 9.
Quality of 10 CFR 50.72 and 50.73 Reports NA NA Reference /Information 1.
2.
3.
4.
5.
6.
NRC review of licensee's PSA completed 08/31/93.
7.
NA 8.
INP0 review / assistance visit completed 09/24/93. Other independent reviews have been conducted in the areas of security management, standby diesel generators, employee concerns program, and operational readiness.
9.
NA 17
.. 3 i
t C.2 ASSESSMENT OF LICENSEE MANAGEMENT:-
l The licensee's management organization should be assessed by NRC staff to ensure that qualified personnel, the proper environment, and resources are provided to ensure that the problems and their root causes have been or are j
being rectified. The organization must demonstrate that it can coordinate, integrate, and communicate its objectives so that they are assigned appropriate priorities regarding safety significance and are completed in a timely manner. NRC reviews will determine if the licensee has effective corporate management oversight and involvement in plant operations and problem resolution.
The licensee's management must appreciate the safety significance of certain issues and ensure that these issues are resolved. The licensee's organization should:
(1) exhibit good teamwork among its subelements; (2) provide strong engineering and technical support for plant activities; (3) possess the internal ability to recognize safety problems, develop and implement adequate corrective actions and verify their effectiveness; (4) possess an independent l
self-assessment capability that can identify and correct performance problems; and (5) have adequate administrative and technical resources available to accomplish the stated goals and objectives.
i I
i 18
.. 3
. - - -l
C.2.1 Management Oversight and Effectiveness ISSUES RESP ORG DATE CLOSED 1.
Management commitment to achieving PANEL improved performance NRR/DRIL 2.
Performance goals / expectations PANEL developed for the staff NRR/DRIL 3.
Goals / expectations communicated to the PANEL
)
staff NRR/DRIL 4.
Resources available to management to PANEL achieve goals NRR/DRIL 5.
Qualification and training of PANEL management NRR/DRIL i
6.
Management's commitment to procedure PANEL adherence NRR/DRIL 7.
Management involvement in self-PANEL assessment and independent self-NRR/DRIL assessment capability 8.
Effectiveness of management review PANEL committees NRR/DRIL 1
9.
Effectiveness of internal management PANEL meetings NRR/DRIL
- 10. Management in-plant time PANEL NRR/DRIL
- 11. Management's awareness of day-to-day PANEL operational concerns NRR/DRIL
- 12. Ability to identify and prioritize PANEL significant issues NRR/DRIL
- 13. Ability to coordinate resolution of PANEL significant issues NRR/DRIL
- 14. Ability to implement effective PANEL corrective actions NRR/DRIL i
19
{
"" 8
i Reference /Information t
1.
2.
3.
4.
5.
6.
7.
8.
9.
i l
10.
11.
12.
13.
14.
20 n.
3
C.2.2 Management Organization and Support:
ISSUES RESP ORG DATE CLOSED k.
Structure of the organization PANEL 2.
Ability to adequately staff the RIV/DRS organization 3.
Effect of any management reorganization PANEL 4.
Establishment of proper work environment RIV NRR/DRIL 5.
Ability to foster teamwork among the RIV staff NRR/DRIL 6.
Ability to resolve employee concerns RIV/DRS 7.
Ability to provide engineering support RIV/DRS NRR/DRIL 8.
Adequacy of plant administrative RIV/DRP/DRS procedures (SPR, PMT, Work Control, ECO) 9.
Information exchange with other utilities RIV/DRS
- 10. Participation in industry groups RIV/DRS
- 11. Ability to function in the emergency RIV/DRSS 12/08/93 response organization
- 12. Coordination with offsite emergency NA NA planning officials Reference /Information I
1.
2.
3.
IR 9347 addressed effect on Emergency Preparedness.
4.
5.
6.
7.
8.
9.
10.
11.
IR 9347.
12.
NA l
21
,,, 3 l
,,-s
1 l
j
]
C.3 ASSESSMENT OF PLANT AND CORPORATE STAFF:
The licensee staff must be capable of recognizing and carrying out their
]
responsibilities to ensure public health and safety. An adequate number of fully qualified licensee staff shall be assigned.- A proactive attitude toward safety issues should be demonstrated in all aspects of operations.
In this-j regard, the licensee staff should display attentiveness to duty, fitness for duty, a disciplined approach to activities, a sensitivity for trends in the-plant, security awareness, an openness of communications, and a desire for j
teamwork that supports effective relations between different groups (e.g.,
i management, operations, health physics, maintenance, engineering, security, and contractors).
C.3.1 Assessment of Staff:
ISSUES RESP ORG DATE CLOSED j
1.
Staff commitment to achieving improved PANEL l
performance NRR/DRIL 2.
Staff's safety consciousness PANEL NRR/DRIL I
3.
Understanding of management's PANEL expectations / goals NRR/DRIL 4.
Understanding of plant issues and PANEL i
corrective actions NRR/DRIL 5.
Morale PANEL NRR/DRIL l
6.
Staff (union)/ management relationship NA NA 7.
Structure of the organization PANEL NRR/DRIL 8.
Effect on the staff of any PANEL reorganization NRR/DRIL i
9.
Resources available to the staff PANEL 6
NRR/DRIL
- 10. Qualifications and training of the PANEL staff NRR/DRIL
- 11. Staff's work environment PANEL l
NRR/DRIL J
- 12. Staff's fitness for duty NA NA
- 13. Attentiveness to duty PANEL NRR/DRIL
- 14. Level of attention to detail PANEL NRR/DRIL 22
.., 3
- 15. Adequacy of staffing PANEL NRR/DRIL
- 16. Off-hour plant staffing PANEL NRR/DRIL
- 17. Rotation schedule for shift workers PANEL NRR/DRIL
- 18. Staff overtime usage PANEL NRR/DRIL
- 19. Amount of contractor usage PANEL NRR/DRIL
- 20. Staff / contractor relationship NA NA
- 21. Understanding of the allegation process RIV/DRS and protection of workers who communicate with the NRC
- 22. Procedure usage / adherence RIV/DRP
- 23. Awareness of plant security RIV/DRSS 09/01/93
- 24. Understanding of offsite emergency NA NA planning issues Reference /Information 1.
2.
3.
4.
SDG problems handled well per IR 9336.
5.
6.
NA 7.
8.
9.
10.
11.
12.
NA 13.
14.
15.
16.
17.
18.
19.
20.
NA 21.
22.
Good procedure adherence noted in IR 9330.
23.
STP Security force management initiatives and the results of an independent security force management assessment were discussed in a management meeting with the licensee on September 1,1993. No restart 23
.. 3
l issues were identified as a result of this meeting or previous security inspection findings.
24.
No restart issues have been identified in this area.
i i
i l
l 24 n.
1 1
i 2
C.3.2 Assessment of Corporate Support:
Not Applicable for South Texas Project.
C.3.3 Operator Issues:
1 ISSUES RESP ORG DATE CLOSED 1.
Licensed operator staffing meets RIV/DRS I
requirements and licensee goals NRR/DRIL 2.
Level of formality in the control room RIV/DRS NRR/DRIL l
3.
Adequacy of control room simulator RIV/DRS 11/02/93 training NRR/DRIL 4.
Control room / plant operator awareness RIV/DRS of equipment status NRR/DRIL 5.
Adequacy of plant operating procedures RIV/DRS NRR/DRIL 6.
Procedure usage / adherence RIV/DRS NRR/DRIL 7.
Log keeping practices NA NA Reference /Information l.
2.
Favorable observations in IR 9330.
Generally effective communications j
and command and control noted, with exceptions, in IR 9334. Mixed i
observations in IR 9336.
3.
Results of 09/27/93 - 10/01/93 exams (IR 93-34) i 4.
Favorable observations in IR 9330.
Good response to SFP level decrease noted in IR 9336. Operator weaknesses contributed to RCS overfill in IR l
9336.
5.
6.
Some favorable observations in IR 9330, but ECO problems noted in Irs 9330 and 9336.
7.
No restart issues have been identified in this area.
i 25
C.4 ASSESSMENT OF PHYSICAL READINESS OF THE PLANT:
The physical condition of the plant is of principal importance not only when a shutdown is the result of a physical event or a hardware deficiency but for other reasons as well, especially following prolonged outages.
The causes of significant equipment problems should be identified and appropriate corrective actions taken. Operational testing should verify that each significant equipment problem has been resolved. As appropriate, the complete spectrum of preoperational and startup testing programs may need to be expanded to cover the more complex types of problems or the effects on plants that have been shut down for extended periods.
The licensee must be able to demonstrate that all needed safety equipment is operational before restart. Systems and equipment need to be available and aligned.
Surveillance tests should also be up to date. The maintenance backlog should be managed at controllable levels and should be evaluated for impact on safe operation. Maintenance must also be capable of responding to equipment failures during startup and operation and should not be hindered by unresolved chronic problems with equipment readiness.
Procedures should be adequate and up to date. The emergency preparedness function both onsite and offsite needs to be capable of protecting public health and safety.
26
l l
t ISSUES RESP ORG DATE CLOSED 1.
Operability of technical specifications RIV/DRP l
systems NRR/DRIL 2.
Operability of required secondary and RIV/DRP support systems NRR/DRIL 3.
Results of prestartup testing RIV/DRP 4.
Adequacy of system lineups RIV/DRP NRR/DRIL 5.
Adequacy of surveillance tests / test RIV/DRP NRR/DRIL program 6.
Significant hardware issues resolved PANEL (i.e., damaged equipment, equipment ageing, modifications) 7.
Adequacy of the power ascension testing PANEL program 8.
Adequacy of plant maintenance program RIV/DRS effectiveness NRR/DRIL i
9.
Maintenance backlog managed and impact RIV/DRS on operation assessed
- 10. Adequacy of plant housekeeping and RIV/DRP equipment storage
- 11. Adequacy of emergency preparedness RIV/DRSS 12/08/93 accountability drills Reference /Information i
l 1.
2.
Fire protection system improvements noted in IR 9337.
3.
4.
5.
TDAFW issues addressed in IR 9338.
6.
7.
8.
9.
10.
Improvement noted in Irs 9336 and 9337.
11.
IR 9347.
l 27
,,, 3
C.5 ASSESSMENT OF COMPLIANCE WITH REGULATORY REQUIREMENTS:
The plant and its prospective operation must not be in conflict with any applicable regulations or requirements of any document authorizing restart (such as license amendments, orders, or a CAL).
Restart should not conflict with any ongoing matter such as an Atomic Safety and Licensing Board hearing.
ISSUES RESP ORG DATE CLOSED 1.
Applicable license amendments have been NRR issued 2.
Applicable exemptions have been granted NA NA 3.
Applicable reliefs have been granted NA NA 4.
Imposed Orders have been NA NA modified / rescinded 5.
Confirmatory Action Letter conditions P.ANEL have been satisfied 6.
Significant enforcement issues have PANEL been resolved 7.
Allegations have been appropriately PANEL addressed 8.
10 CFR 2.206 Petitions have been NRR 07/08/93 appropriately addressed 9.
Atomic Safety and Licensing Board NA NA hearings have been completed Reference /Information 1.
Under evaluation 2.
NA 3.
NA 4.
NA 5.
6.
7.
8.
Saporito Petition acknowledgement letter of 07/08/93 9.
NA 28 a.
2
l C.6 COORDINATION WITH INTERESTED AGENCIES / PARTIES:
Coordination with other interested parties and agencies is important to ensure that concerns and requirements of these organizations are factored into the restart authorization.
ORGANIZATION RESP ORG DATE CLOSED 1.
Federal Emergency Management Agency RIV/NRR 2.
Environmental Protection Agency NA NA 3
Department of Justice PANEL 4.
Department of Labor PANEL 5.
Appropriate State and Local Officials RIV 6.
Appropriate Public Interest Groups RIV 7.
Local News Media RIV Reference /Information I.
2.
NA 3.
4.
5.
6.
7.
l l
29
.. 3
D.
PLANT SPECIFIC STARTUP ISSUES i
The list of plant specific restart issues was developed from a review of the Diagnostic Evaluation Team Report, the Confirmatory Action Letter and supplements, the licensee's Operational Readiness Plan, routine and special NRC reports, the allegation process, and NRC staff actions assigned by the Executive Director for Operations following the Diagnostic Evaluation. NRC Inspection Report 50-498/499-9331 identified and assigned an Inspection l
Followup Item for each item related to issues which require resolution prior to the restart of either STP unit. This table will be updated periodically to reflect the status of inspection activities at STP.
The table following this page lists the plant-specific restart issues and their current status.
I
^
30
.. 3
\\
t RESTART ISSUE RELATED ITEMS DATE CLOSED 1
Turbine-driven Auxiliary Feedwater Pump 9331-07(9338-0), 08(9338-0), 09(9338-0),
Reliability and Testing Methodology 10(93"8-0),43(9338-C),50(9338-0),
71(9338-C) 9305-04(9338-C), 05(9338-0), 07(9338-C)
Unit 1 LER 9307(9338-0)
Unit 1 LER 9304(9338-0) 2 Station Problem Report Process, Threshold, 9331-Ot:(9338-0), 18, 23, 25, 26, 27, 28, Licensee's Review of Existing Reports for 67 f
Issues Affecting Operability and Safe Plant 9235-02 Operation 9224-01 9321-01(9333-C) 9322-02(9333-C) 9308-02, 04 3
Service Request Backlog, Including Reduction 9331-02,03(9340-0),07(9338-0),
Accomplished During the Current Outages and 08(9338-0),09(9338-0),29,31,37,38, the Licensee's Review of Outstanding SRs for 39, 47, 49, 62, 79, 80 Issues Affecting Equipment Operability, Safe Plant Operation, and Operator Work-arounds 4
The Postmaintenance Test Program, Including 9331-03(9340-0),04(9337-0),07(9338-0),
Corrective Actions in Response to-Violations 10(9338-0),13(9339-0),14(9339-C),15, and Other Process Improvements and the Basis.
51,63,68(9339-C),79 For the Licensee's Confidence That Equipment 9226-03(9339-C)
Removed From Service for Maintenance is 9320-02(9339-C) 2 Properly Restored to an Operable Status 9305-01, 05, 07 Unit 1 LER 9204(9339-C), 9207(9339-C),
9214(9339-C),9216(9339-C),9305 I.
i 31
,,. 3 i
4 4
_..-__.-.--..-..-_.,____.-u___.---..--__-..--__.__.w------_--,__u___-.__-__.__-
s-w-
a -
u---_ -,-w s-- --
w x
t 6
RESTART ISSUE RELATED ITEMS DATE CLOSED 5
The Outstanding Design Modifications, 9331-02(9337-0), 04(9337-0), 08(9338-0),
Temporary Modifications, and Other Engineering 12, 16, 18, 19, 20, 21, 30, 31, 40, 41, Backlog Items, Including the Licensee's Review 42, 44, 45, 48, 52(9338-0), 64, of These For Issues Affecting Equipment 65(9340-0),77,81 Operability, Safe Plant Operation, and 9208-01 Operator Work-arounds 9306-07 9315-01 Unit 1 LER 9220, Unit 2 LER 9204 6
Adequacy of Operations Staffing 9331-01(9340-0), 03(9340-0), 24(9340-C),
56(9340-0),57(9340-0),59(9340-0),
60(9340-C),65(9340-0),66(9340-0),
73(9340-0) 9116-02(9340-0) 9304-03(9340-C), 04(9340-C) 9311-04(9340-C) 9322-01(9340-C)
Unit 2 LERs 9305(9340-C), 9312(9340-C) 7 Adequacy of Fire Brigade Leader Training and 9331-04(9337-0),33(9337-C),75(9337-0) 11/23/93 Qualifications 9337 8
Adequacy of Fire Protection Computers and 9331-02(9337-0), 04(9337-0), 17(9337-0),
Software, the Licensee's Success in Reducing 22(9337-0), 58(9337-C), 75(9337-0) the Number of Spurious Fire Protection System 9235-06(9337-0)
Alarms, and Other Fire Protection Hardware 9309-01(9337-C)
Problems 32
.. 3
RESTART ISSUE RELATED ITEMS DATE CLOSED 9
Licensee Management's Effectiveness in 9331-04(9337-0),05,06(9338-0),
Identifying, Pursuing, and Correcting Plant 17(9338-0), 18, 22(9337-0), 23, 25, 32, Problems 34, 35(9338-0), 37, 46, 54, 55, 56(9340-0), 61, 62, 65(9340-0), 67, 69, 70(9338-C),72(9338-C),73(9340-0),80, 82 9321-01 9322-02 9224-01 9217-02, 04 9303-01 9308-02, 04 Unit 1 LER 9204 10 NRC Review of the Effectiveness of the 9331-78 Licensee's SPEAKOUT Program 11 Standby Diesel Generator Reliability 9331-08(9338-0),09(9338-0),11,12,13, 16, 19, 28 9214-03 2
l 9221-03 9305-01 9315-03(9330-C) i Unit 1 LER 9305
~
12 Essential Chiller Reliability 9331-10(9338-0), 13, 20, 21, 44, 45, 74 9224-03 Monitoring of the Licensee's System 9331-35(9338-0),53 13 Certification Program l
Adequacy of the Licensee's Resolution of the 9319-01 through 07 14 Reliability and Operability of the Feedwater 9324-01 Isolation 8ypass Valves Unit 1 LER 9317 Unit 1 LER 9320 33
,,, i i
.,#.,.m
..e,
. ~ -.,., _.~ ~.,,. -.,.. -..
--...,..-<_-..m
=-.
e-i i
RESTART ISSUE RELATED ITEMS DATE CLOSED 15 Tornado Damper Issues 9331-76(9342-C) 11/19/93 9342 16 Emergency Preparedness Accountability Issues URI 498;499/9325-02(9347-C) 12/08/93 Reference /Information 1.
Resolved with exception of Mode 3 testing in IR 9338.
2.
3, 4.
Progress noted in IR 9339.
5.
6.
Progress noted in IR 9340.
7.
Closed in IR.9337 dated 11/23/93 8.
9.
Favorable observations with respect to fire protection issues in IR 9337. -Favorable comments with respect to TDAFW issues in IR 9338.
Favorable observations with respect to operator staffing issues in IR 9339.
Favorable observations with respect to tornado damper issues in IR 9342.
10.
11.
12.
13.
Favorable observations -in IR 9336.
14.
15.
Closed:in' IR 9342 dated 11/19/93 16.
Closed in IR'9347 dated 12/08/93.
t 17.
r 34
4 I
I e
j l
E.
RESTART INSPECTIONS RESP SCHEDULE INSPECTION ORG LEAD 1
TDAFW PUMPS DRP MAS 10/18/93 2
SPR PROCESS, THRESHOLD, REVIEW DRS TOM 10/12/93 4
RESULTS
+RI 12/13/93 3
SERVICE REQUEST BACKLOG STATUS AND DRP MAS 11/29/93 REVIEW, EFFECT ON EQUIPMENT LDG 12/06/93 y
OPERABILITY, SAFE OPERATION, MFR OPERATOR WORK-AROUNDS 4
POSTMAINTENANCE TEST PROGRAM DRS TOM 10/25/93 RBV 11/29/93
~
5 ENGINEERING BACKLOGS DRS TFW 11/15/93 6
OPERATIONS STAFFING DRS/DRP JLP 11/01/93 l
JIT 11/29/93 7
FIRE BRIGADE LEADER QUALIFICATIONS DRS GLC 10/18/93 8
FIRE PROTECTION COMPUTERS DRS GLC 10/18/93 i
9 MANAGEMENT EFFECTIVENESS IN DRP/DRS/DRSS EACH IDENTIFYING, PURSUING, AND INSPECTION CORRECTING PLANT PROBLEMS 10 SPEAK 0UT REVIEW DRS/HQ DAP 11/29/93 11 EDG ISSUES DRS/NRR TFW 11/08/93 12 ESSENTIAL CHILLER ISSUES DRP/NRR MAS 4
13 SYSTEM CERTIFICATION DRP/DRIL SRI /0 RAT ONG0ING 14 FEEDWATER ISOLATION BYPASS VALVES DRS DAP 11/15/93 i
15 TORNADO DAMPERS DRP/NRR MAS 11/01/93 16 EP ACCOUNTABILITY DRSS BXM 11/18/93 1
17 LICENSEE'S READINESS ASSESSMENT RIV/NRR PANEL 12/93 18 ORAT DRIL JBJ 12/06/93 01/05/94 0
35
.. 2
.