ML20198K948
| ML20198K948 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/22/1997 |
| From: | Travers W NRC |
| To: | |
| Shared Package | |
| ML20198K919 | List: |
| References | |
| PROC-970722, NUDOCS 9801150137 | |
| Download: ML20198K948 (57) | |
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RESTART ASSESSMENT PLAN HILLSTONE STATION JJ'"~
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'r DATE: JULY 22,1997 APPROVED:-
WILUAM [ TRAVERS DIMCTOR, SPECIAL PROJECTS N
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MILLSTONE
, RESTART ASSESSMENT PLAN
1.0 BACKGROUND
The three Millstone units are shut down to formulate responses to a series of 10 CFR 50.54 (f) letters requiring them to affirm their compliance with the l
conditions of each unit's license and the regulations.~ The NRC performed a series of f
inspections at Units 2 and 3 with r /O-wrson Specialinspection Team (SIT) to ascertain the extent of their compliana Currently, the results of those inspections are under assessment by the team and Nhc management. The licensee initially focussed on Unit 3 as the lead plant for restart. However, as a result of a licensee reorganization which occurred on October 1,1996, each Millstone unit was assigned a recovery manager who was an executive on temporary loan from another nuclear utility. Resources originally assigned to Unit 3 from the other units were retumed to their respective units. Each unit has been tasked with establishing their own restart plan and whichever unit is ready will apply to restart first. Hence this restart assessment plan has been expanded to include Manual Chapter (MC)-0350 evaluations (see paragraph 3.0) for all three units.
On June 28,1996, the Executive Director for Operations (EDO) issued a letter to the licensee that stated the Commission had decided to make the three Millstone units a Category 3 on the Watch List and would vote on the restart of the Millstone units, it is the intent to implement the appropriate aspects of NRC Manual Chapter 0350, " Staff Guidelines for Restart Approval" for the restart of all three units. The NRC will schedule and implemerit its inspection program after the licensee has indicated that the individual activities necessary for restart are complete and ready for inspection.
The NRC has been dealing with Northeast Utilities on broader performance issues which go beyond the 10 CFR 50.54(f) concerns. These broader concerns are considered centributory causes for the cueront poor performance, which the 10 CFR 50.54(f) issues are a subset. These issues have been formalized by the licensee in a program titled " improving Station Performance" (ISP) and are topics that will be addressed by the licensee and reviewed by the NRC Millstone Restart Assessment
' Panel. A meeting was conducted on April 30,1996, and disclosed that the licensee was not adequately managing the program or tracking progress.
' The salient concerns embodied in the ISP include leadership, communications (employee concerns), the corrective action program, procedural adherence and procedure upgrades, work planning and control, and operational enhancements. The NRC Restart Assessment Plan will focus on the broader issues of the ISP and
-licensee self-essessments and management oversight, recognizing the necessity to ensure adequate closure of the 10 CFR 50.54(f) process. The NRC plan for inspection of the Improving Station Performance issues is discussed in more detail in
.Section 3 of this plan.
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On' November 3,1996, the agency establisned the Special Projects Office (SPO) to consolidate NRC efforts under a single Senior Execu6 a Service (SES) manager, who reports to the Director of the Office of Nuclear Rest.+. Regulation (NRR). The Director, SPO assumed tho' authority and responsibilities of the Regional Administrator and the Associate Director of Projects.
2.0 10 CFR 50.54ff) Activities Each Millstone unit has been requested to submit infomistion describing actions taken to ensure that future operations will be conducted in accordance with the terms and conditions of the operating license, the Commission's regulations, and the Final Safety Analysis Report. In a May 21,1996. letter, the NRC requested Northeast Utilities (NU) to provide for each unit its plan for completing the licensing bases reviews.
To aid in NRC understanding of how deficiencies were identified and dispositioned, the NRC's May 21,1996, letter also requested that NU provide for each Millstone unit a comprehensive list of design and configuration deficiencies and information d
related to how each defbiency was identified and will be dispositioned.
On August 14,1996, the NRC issued a Confirmatory Order establishing an independent Corrective Action Verification Program (ICAVP). The independent effort will verify the adequacy of NU's efforts to establisti adequate design bases ar.d design controls, including translation of the design bases into operating procedures and maintenance and testing practices, verification of system performance, and implementation of modifications since issuance of the initial facility opeisting licenses. The NRC oversight of the ICAVP and activities will be in addition to the activities described in this Restart Assessment Plan. The results from this program will be incorporated into this restart plan and considered a significant part of the decision regarding recommended restart. The deficiencies found by the licensee as a result of the 50.54(f) letters will be evaluated by the Millstone Restart Assessment Panel to identify restart issues.
3.0 MC 0350 Process Millstone Unit 1 entered a routine refueling outoge on November 3,1995. On December 13,1995, the NRC sont a 10 CFR 50.54(f) letter requiring the licenses to certify compliance with the regulatory requirements before restarting the unit. At 4
i the January 1996 Senior Management Meeting, the site was placed on the " Watch List" for various reasons, including a concern for regulatory compliance.
Subsequentlyi Millstone Units 2 and 3 were sent similar letters which required responses before restart.
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3 The NRC Inspection' Manual, Manua! Chapter (MC) 4350, " Staff Guidelines For Restart Approval", provides guidelines and a list of tasks and activities that must be considered before a plant that has been shutdown for cause can restart. Because of NRC concoms relating to the licensee's management effectiveness, the appropriate aspects of MC 0350 will be applied to the restart of Units 1,2, and 3 to ensure apolicable requirements have been met (Enclosure (4).
i The Director, SPO, in coordination with the Deputy Executive Director for -
- Regulatory Programs, and the L'irector of NRR, will make a recommendation regarding restert. NRR and the SPO willinform the Commission of the staff's and licensee's restart activities through Commission papers, or communications to the EDO. The Commission will then vote on whether to approve the restert of each Millstont unit.
3.1 SPECIAL PROJECTS OFFICE 4
The SPO was created on November 3,1996, to oversee the restart of the Millstone unks. The plan was to consolidate tt,e NRC resources devoted to the restart efforts under one SES manager. The office is organized into three primary elements, licensing, inspection, and independent corrective action oversight. The Licensing Eranch will administer the typical licensing actione performed in NRR; the inspection Branch will implement the inspection programs, normally managed from the region, and the independent Corrective Action Verification Program Oversight Branch will oversee the licensee's licensing and design bases review process.
Within the SPO, the Restart Assessment Panel (RAP) will meet to assess the j
licensee's performance and their progress in completing the designsted restart activities. The RAP Q composed of the Director, SPO (chairman); the Deputy Directors of Licensing, inspections, and independent Corrective Actions Verification Program Oversight; the Project Managers for the three Millstone units; the inspection Branch Chief, the Senior Resident inspectors for the three Millstone units, and the appointsd Division of Reactor Safety representative. The function of the Millstone RAP is described in MC-0350.
3.2 Mili ETONE OPERATIONAL READINFRE PLAN i
On July 2,1996, NU submitted the Unit 3 Operational Readiness Plan, which was discussed at the July 24,1996, meeting and updated at the August 19,1996, meeting. However, the licensee has replaced all of the line managers (President, Vice Presidents, and two of the three unit oirectors) (n the recent past. With this replacement, the submitted plans for Unit 3 and the proposed plans for Units 1 and 2 are being changed substantially. The RAP will review these plans and hold periodic meetings with NU, open to the public, to discuss the schedule for implementation and coordination of NRC restart activities.
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The deficiency lists associated with the restart plans for each unit, which will be updated periodically by.the licensee, includes restart and deferred items, and will be audited by the NRC to verify the acceptability of the criteria used to defer items -
from the restart list.
3.3 CORRECTIVE ACTION PROGRAM The NU corrective action program has been week in ensuring comprehensive and effective corrective actions. There are many !nstances of narrowly focused corrective actions that failed to embrace all aspects of the underlying problem.
Additionally, thz licensee has failed to follow up on corrective actions te ensure they were effective. Consequently, the RAP has determined that any restart effen l
should examine the current state of the licensees corrective action program.
Because of the la;ge number of Adverse Condition Reports (ACR) being identified by the licensee's staff, the resident and regional inspection staff will concentrate on Issues for each unit identified by the ACR process and audit the licensees corrective actions for completeness. The staff is periodically selecting ACRs for review, based on the licensee's assigned level of importance, or their Fisk significance, as perceived by the resident staff. Additionally, other ACR's will be examined to provide a spectrum of safety significant and lessor risk issues. These selected ACRs will be added to the SIL for each unit, which are Enclosures 1,2, and 3 to this plan.
j The intent is to primarily assess the corrective action program.while dealing with the safety significant technicalissues. Examination of the corrective action program needs to review the Action Requests (AR) from the Action item Tracking and l
Trending Systum (AITTS) program, which is an extension of the ACR process, and
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commitments regarding violations and inspection items. Further, a significant input to assessing the licensee's corrective action program is derived fiam the normal inspection program where valuable insights regarding the effectiveness of corrective actions are routinely collected from the technical safety inspections.
l Additionally, the NRC Independent Corrective Action Verification Oversight Branch will assess the licensee's corrective actions for degraded and non-conforming conditions. Finally, the Operational Safety Team inspection (OSTI) will audit portions of the corrective action process during the courso of its activities.
Demonstration of improvements in the process will be judged by the completeness of the licensee's corrective actions for each of the inspected ACR's. There must be a high ratio of successfully completed ACR's to the total population inspected.
There should only be minor comments regarding the processing, ev3ustion, directed corrective actions and closure of an issue.
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5 3.4 WORK PLANNING AND CONTROLE (C.d.1' Work planning and controls are other areas that the licensee N shown a weekness.1 The ability to plan, control, and complete work..undamental to achieving adequate corrective actions. Effective work planning and controls are prerequisites for reclucing and managing backlogs. Weak work planning and control was demonstrated during the Unit 2 outage, wherein, tagging boundary vblations i
resulted in an extensive effort by the licensee to correct. Work control and planning were also issues at Unit 1, which resulted ;n a management meeting.
There will be a complete review of the Automated Work Order (AWO) process by the residsr.t or regional staffs. The automated work order process is an integral part of the work planning and control rystem and is instrumentsn establishing the scope of the work, providing the appropriate procedures, are establishing the tagging boundaries. Cormequently, the Unit 1 resident staff has seen directed to use the hvallable initiative inspection hours to do a comprehensiv3 inspection of the 4
AWO process, which is a site-wide process, The OSTI will assess the engineering and maintenance backlogs during its f
operational readiness inspection. The OSTI will determine if there are vfety significant irsues that must be resolved befort restart.
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3.5 PROCEDURE UPGRADE PROGRAM fC.2.2.a)
The quality and adherence to proceduras has been a chronic problem at the Millstone site.- The issue was an element in " improving Station Performance" and was one of the subjects of discussion at the periodic meetings between NU and the NRC. In response to NRC concems, the licensee developed the Procedure Upgrade Program in the early iggO's to improve station procedures.
The resident inspectors will relate procedural inspection findings back to the procedural upgrade program (PUP), identifying whether the procedures reviewed during the course of an inspection have been upgraded and characterize the quality of the document. This will establish a basis for assessing the effectiveness of the licensee's PUP. The NRC staff will develop an inspection plan for examining selected portions of each unit's individual efforts.
3.6 OVERSIGHT (C.1.4 i The licensee has identified its oversight function as deficient through self-assessments and extemal and internal audits and as a contributing factor in the licensee's declining performance. The report of Annenament of Past ineffectivannas 3 Reference to applicable MC-0350 section Revision 3/24/g7
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of indanandant overataht by the Yankee Atomic Electric Company (YAEC),
examined the f ailure of Quality Assessment Services; the Independent Safety Evaluation Group, and the Nuclear Movivw Board (NRB) to identify the deficient FSAR control process and the radioactive waste conditions. They found that management did not support these functions adequately.
In addition, the Joint Utilities Management Association (JUMA) issued its report on July 17,1996. One conclusion war that the quality assurer'cw (QA) program audits, surveillances, and inspections were not effective in the implementation of their mission and resolution of identified problems. In addition, the JUMA audit found that recommendations for improving OA effectiveness identified in previous OA internal and external assessments have not been addressed.
The NRC assessment of the nuclear oversight function is addressed as part of the RAP's review of the ISP program and through insights gained from the normal-inspection program, in addition, the NRC will perform a special inspection of the oversight function using the services of its Human Factors Asses:..aent group. Late
'in the restart process for each unit, there will be an inspection to evaluate tha effectiveness of the oversight groups and management's utilization of the oversight process. There should be positive iridications that the oversight function has been mada en integral part of the licensee's management team assessment process. The oversight f:Jnction should result in meaningful findings, have access to lirie management, and provide assessments of process and program effectiveness through periodic reports, There should be evidence that the reports are forwarded to the responsible manager and that they have dealt with the contents appropriately.
Oversight should be adequately staffed with qualified and experienced personnel.
The audit and surveillance programs need to be clearly defined, proceduralized, and l
implemented with established schedules.
2.7 ENFORCEMENT Outstanding enforcement items will be reviewed by the resident inspectors to determine if any issues require closure before plant restart. The agency is currently accumulating escalated enforcement items concoming the spent fuel pool and
- design bases issues which may require licensee response before recommending restart of each umt. There are also potential enforcement items that will result from 4
the efforts of the Office of Investigations, the allegation process review group, the Office of the inspector General, the Special inspection Team, routine resident and regional inspsetion efforts, and the 10 CFR 2.026 petition process.
A Pre-decisional Enforcement Conference was held with the licenses on December 5,1996, to discuss 04 individual apparent violations. The licensee did not contest any of the violations at the conference, and the staff is in the process of Revision 3/24/97
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7 finalizing the enforcement package. Once enforcement actions have been taken,.
the NRC will evaluate the licensee's corrective action to those enforcement actions which are.letermined to impact restart of each unit.
3.8 EMPLOYEE CONCERNS The Millstone site has had a chronic problem in dealing effectively with employee concerns. The NRC continues to receive en inordinate quantity of allegations from the staff at the Millstone site. The current series of 10 CFR 50.54(f) letters were initiated due to NRC concerns regarding design basis issues at Millstone, as well as an allegation, and a subsequent Millstone 10 CFR 2.206 petition, dealing with the Unit 1 spent fuel pool. The NRC has issued two enforcement actions for harassment and intimidation to NU in the past three years and has a current escalated enforcement action pending.
The NRC initiated two task groups to examine the Northeast Utilities handling of employee concerns, and the recent layoffs that affected several previous allegers.
The task group examined NU's handling of employee concerns and identified a number of root causes for the licensee's problems in this ares. The task group also i
concluded that past problems and their root causes still remain. Subsequently, the NRC issued an order, dated October 24,1996, requiring NU to c.steolish a comprehensive program to address employee concerns, and hire an independant party to oversee the implementetkn of the program. The output from these two taan groups and the licensee's response to the order will be reviewed for restart i
issues.
3.g SIGNIFICANT ISSUES LIST The technique to be used for the restart will be to reach agreement with the licensee on its restart issues list, have it impose controls on adding or deferring items from the list, have the resident inspectors review the list to ensure it includss issues of interest to the NRC, and have the residents review the deferred list to ensure appropriate rationales for deferral have been documented (see item 8.4.3. of MC 0350). As a result of the 10 CFR 50.54(i) activities, the licensee initially determined that, for all three Millstone units, hundreds of items did not meet criteria for inclusion as a restart item. The resident inspectors, augmented by headquarters staff, are reviewing these lists periodically and confirming that the licensee is performing on adequate assessment of the discrepancies. Thic process will be ured in the testart assessment of each unit. The RAP will determine that licensee's restart 6 sues list includes appropriate restart items from the licensee's programs such as ACR, AR (AITTS), engineering work requests, and commitments.
The enclosed NRC Significant lasues Listr for all Millstone units (Enclosure 1, 2 and
- 3) contain some of the items that are being used to audit and evaluate licensee Revision 3/24/g7
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programs such as the corrective action process and significant safety / regulatory technical issues, Restart issues will meet at least one of the following criteria: -
t 1.: Resolution of the issue is required to ensure safe operation of the facility to include satisfaction of the technical specifications or licerssing basis..
2i inspection of the issue will provide en insight to en identified programmatic deficiency such as the corrective action system.
3.
Inspection of the issue will provide assessment of management effectiveness or personnel performence.
3.10 - RESTART INSPECTION t
Selected portions of NRC MC-93802, " Operational Safety Team inspection, will provide the framework for a team inspection of each unit during the restart process.
The procedure scope will be modified to address the pertinent issues at Millstone.
The inspection will cover self assessments by the licensee, the licensee's
_ implementation r;f N startup plan, control room observations during the approach to i
criticality and power ascension, selected systems readiness inspection and observation of management oversight.
The resident inspectors will provide close monitoring of each unit during mode changes to ensure compliance with each unit's technical specifications and FSAR design bases.
L 3.11 PLANT PERFORMANCE REVIEW On March 19,1997, the Millstone Oversight Team conduct W e Plant Performance Review (PPR). The PPR was used to identify the issues that needed to be inspected for the Millstone station. The review identified several issuer. that warrant NRC inspection before plant restart of the unit. The unit specific issues, as well as station wide issues identified by the PPR, are contained in the SIL for each unit as inspection items.
3.12 LICENSING ISSUES Each Millstone unit plans to submit or has submined sicensing issues (amendments,
' untosolved safety questions, relief requests, etc.) which will impact the restart process.. The SPO Licensing Drawh will disposition each applicable issue prior to L
restart. The status of NRR actions concernir:p each issue is documented in Enclosure (5) of this plan.
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Enclosures:
(1).
Significant items List'- Millstone Unit 1 (2)' - Significant hems List Millstone Unit 2 -
1-(3)
Significant hems List Millstone Unit 3 _
(4) -- ! MC-0350 Restert Approval Checklist All Millstone Units -
(6)~
Licensing Amendment Sequests A
h 3
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5 ENCLOSURE 1 SIGNIFICANT ITEMS LIST - MILLSTONE UNIT 1 4
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7 MILLSTONE RESTART ASSESSMENT PLAN ENCLOSURE (1)
Millstone Unit 1 S!anificant items Ust REFERENCE MILLSTONE UNIT 1 INSPECTION ITEM RESP STATUS SPO 1
AcR:0114e FSAR Adequacy for Restart (L)
DRS 2
ACR:01535 While de watering spent resin, the waste temperature in the liner raised from 90 to 310'F SPO 3
ORDER Employee Concerns Program eSenior management has Created difficult Working (L)
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ACR M19 -
environment 0921 EA: 96 59 MC 0350 C.1.4.e.
C.5.d. c.2.2.b 4
Mc 0350 Review enforcement and unresolved items for restart SPO (l)
C 5.e issues 5
Mc 0350 c.5.f Review allegations for restart issues SPO(l)
SPO(L) l Review all operability determinations and by pass SPO (l) s jumpers before restart DRS 7
LER: 96 22 Fatigue cycle open items URI: 92 30-2 s
Mc 350 Security issues - Corrective Action DRS C 3.1.1; eel: 96 0515 97 03 01 (02H03);
VIO: 96-09 20 9
Review licensee event reports for restart issues SPO (1) 10 ACR: 05373 Material, Equipment and Parts SPO(L)
M1 97-0358 List (MEPL) Program DRS 11 AcR: 96106a.
RPS System SPO (1) 7245 eScram solenoid pilot valve replacement 12 LER: 964s Overlap testing of RPS/ESF DRS GL 96-01 ACR: M197-045 Revised 7/16/97 i
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REPERENCE MILLSTONE UNIT 1 INSPECTION ITEM RESP STATUS l'
13-Ti ssis/109 -
Motor Operated Valves (GL 8910) -
DRS I
URI:94 005 02,94 005 04,96 001.-
01,96 006 05 LER:9652-ACR: 03689. -
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Surveillances Program Review SPO (1) 0992-LER: 9618 -
V10:96 007 02 LER: 94 42 1s ACR:10700 Control /Use of Vendor information DRS l
(U 31 16:
ACR:M196 Redwaste recovery / configuration.
DRS 0918 M1 97-0240,0241 einsufficient management support for maintenance of
- eel:96-003-01 LER: 97 001 redweste MC 0350
- RW offlunn: isolation valve GA classification C.2.2.c 17 eel: 96 09 06, Corrective Action Program Effectiveness SPO (1)
Update 97 02 01; gg,G7-02 URI:07 02 02:
- Review licensee corrective action programs for SPO 96 01 01:
m: 96 04 effectiveness to include ACR's.
(O)
ACR: Mi So-
- Corrective actions have been ineffective in resolving 007' problems M196 0823, M1 961035, M197 0342, 0343 MC 0380 C.1.1, C.1.3, C.1.4.d.
C.2.1.h.
C.3.1.s is-Review 0737 action items for completion and SPO (1) adequacy 19 Review engineering backlogs SPO (1) for restart issues 20 oR0eR implementetion of CMP /ICAVP corrective actions.
-SPO M C03s0 C.s.s go) 2 Revised 7/16/97 i.
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REFERENCE MILLSTONE UNIT 1 INSPECTION ITEM.
RESP STATUS DRS-21-Acm: 03117 eSingle failure cen disable both trains of e...orgency
[g'0[817,8b power source LNP lockout relay.
77,
eReview LNP integrated procedure and resutts ACn: M197 0323. os17, eLNP post testing does not meet RG 1.41 Lan: 94 2041 Requirements s DRS-
- 22-unhs4 o.4-01 SRV's
[c("o,$07 e setpoint drift resolution e accelerated testing M:.es.-
osta,t120 e electric lift modification adequacy
- electric lift setpoints not fully evaluated SPO 23 Acm: s2s4 Configuration Management / Design Control Process C%239.M1 (f)/SPO (Pa t of ICAVP Phase 1)
(0) e64sts, M1-es oose, M3
. 96 0345, M1 4 10083
- Review 50.54 issues for restart issues N,,,3 _
eUnit 1 design deficiencies and issues trends
- Review open DBDP items for startup issuas sei:ss-os os MC 0350
- Review station blackout self assessment items for C.2,1.s.t ~
startup issues eSignificant differences between design bases and as-
. veo. 37 02 o7 built oField changes to plant modifications not reviewed for cause 24 Review FME SPO (I)
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o FME deficiencies trend for SFP and RX cavity 2
M1 se-o72s, o Debris identified in spent fuel pool M1 ## o#13, e Adverse trend identified in Unit 1 FME program M197 o221 e Fuel Pool foreign material and storage controls e LP 24D stuck open due to foreign material as ACR:07478.
Inadequate design modifications DRS y[,,
e installed wrong material (pressure rating) for LLtJ connections
-as ACR: oss22 Current CWDs do not show modifications to equipment SPO (i) i 3
Movised 7/16/97 l
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REFERENCE MILLSTONE UNIT 1 INSPECTION ITEM RESP ST/\\TUS 27 ACR: 06te3 Fuse control program inadequate DRS LER:96 31.96-17 URI:96-oo4 06 2s Aca:126ss.
LOCA analysis does not account for instrument DRS uncertainty during surveillance testing 29 PPR E.1 Operator acceptance of degraded onditions, lack of SPO (l)
"c Oa" ownersh!p, O.D.'s accept degraded conditions,-
gd temporary mods, etc.
30 AcR:M106-Work Planning and Control SPO (1) 0343.M1 96-
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- Audit the AWO process PPRE 2
- Significant long standing work management eel:96 0a-01 weakncsses Mc
- Failure to completely impleme M. and document 2
recommendations of AWO task force report of 1/1995 eTroubleshooting 31 PPR E.2 Post maintenance testing / maintenance F/U inspection SPO Vio:96-001*
(1)/DRS 02.94-031 01; MC 0350 C.4.h 32 URl:96 006 04 Sawork SFO (i) 33 LER:P6-40.96-Seismic luues DRS Update 49,9 'c 51 lg; g7,
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- Seismic review seismic modifications (FWCl, A-46, 01 E
uni:s6-os 04, 79 02/79 14, NUSOER) 96 os os.s7
- Seismic 11/1
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- Verify resolution of A 46 outliers 0
Mi.96 0696, eCRD operability M197 0345 eSEP Topic III 6 Close out 0412..M1 96-oa43 4
Revised 7/16/97
REFERENCE MILLSTONE UNIT 1 INSPECTION ITE,M USP STATUS 34 1R: 95 s2 Spent Fu61 Pool DRS IFl:96-004 02 LER: 96 013 ACR:M1 96-eSFP Cleanup 64a M1 97 eReview resoiution of Spent Fuel Poolissues g{1g ssess and disposition numerous open items in IR95-oos2,0035,
- Unanalyzed condition due to indeterminate boraflex M197 0365, degradation
- oye, eLoad drop analysis (Fuel) e,
,7, 01 o1 35 Review Peg Guide 1.97 modifications DRS as AC Mi 96-NRC Information Notices IENS have incomplete or SPO (1)
Inaccurate responses 37 ACR:M1 96-Control rod blades in spent fuel pool lifted lhadvertently SPO (l)
Update
$:96-006-02 with tri oc filter IR:97 02 Se A R M196*
Ineffective program to monitor and control fasteners DRS LEM: 96 27 eel:96 04 05 39 ACR:M196-Adverse trend identified in the control of contracted DRS 0564 services 40 ACR:M1 96-M&TE program is ineffective GPO (1)
Update 1R:97 01 c1 ACR:M1 96-Process for controlling distribution and use of SPO (l)
M1 97' document 6 (procedures) is ineffective C2 ACR:M1 96-Potential deviation from toch specs when changes SPO (1) osio made to Unit 1 organizational structure 43-ACR:M196 Emergency Preparraess Program DRS o648,M1 97-0071 NU letter (Including Organ;2ation/ Staffing / Dose Assessment sis 195 Capability)-
2/10/97 MC o350 C 3.1 m C 2.2 s C 2 2.h 44 ACR:M196-Equipment Environmental Qualification (EEO) Program DRS' os76 5
Revised 7/16/97
REFERENCE MILLSTONE UNIT 1 INSPECTION ITEM RESP STATUS 45 ACR:M1 96-Components in control rod drive system (suction filters DRS
" 88 and associated piping, valves and fittings) may not meet the original design requirements 46 AcR.M1 96-Insufficient personnel for key leadership programs SPO (I) 0924 47 ACR:M196-PM tasks on plant equipment not performed SPO (1) 0925 MC 0350 C.4.1 de ACR:M1 96-Management direction insufficient for system DRS 2s
[c 350 engineering C.2.1.s 49 AcR:M1 06-System and design engineering work management SPO weaknesses (0) fe 350 2
C.2.1 so AcR:M1.sc.
Training for engineering personnel net e8fectively SPO implemented c 350 c.3.1.e 51 ACR:M1 96-Improvements needed in TLD process and program DRS 0933 g
52 ACR:M1 96-Chemistry issues DP.'s
- 34 *MI'88'
- Adverse chemistry conditions increase potential for IFl:96 oo416 corrosion eWeaknesses in chemistry monitoring, trending and evaluation 53 URl: 9612 01 Procedure Adequacy / Procedure Upgrade Program SPO (1)
^cn Mi &
e Openting procedure deficiencies hinder operators
,,o '
p,,
o,3o
- Deviation from operations procedures during Mc 0360:
simulator transients C.3.1.k.
- Verify off normal and general operating procedures
[3$',O revisions / adequacy C.2.2.d.
- EOP's C.2.1.b URl:S7 0102 64 ACR:M1 96-Component and system degradation during plant SPO (l) 09n shutdown 55 ACR:M1 96-Degraded instrument air system quality SPO (1) i o912 l
l 8
Revised 7/16/g7 i
1-i REPERENCE MILLSTONE UNIT 1 INSPECTION ITEM Resp STATUS DRS Update se v o w 4o7.os Appendix J resolution IR:37 02
$'j'08' einadequate test!ng elmplementation of Appendix J modifications Acn: esse, M1 es-eVerify the basis for not Appendix 'J' testing tne 0188."147' ECCS suction valves "j74 eAdequacy of the basis for the shutdown cooling system classification as a closed loop system 4e i
DRS Updete 67 Lan: es424, LLRT Proprom Review IR:97 Yg gyg,
- Foodwater system configuration not allow complete 2 es 02 drein, accept LLRT os.umj
- Containment isolation check volve f ails inform LLRT l
uni:s741 os;sel:9743
inboard containment iso'stion volves LP.14A & LP.1431 f
DR$
se Aca:ui.es-SSGT issues resolution osts,97 N' "*
elmplementation of a low flow loolation modification Dav: nots-
- Resolution of all outstanding issues that could effect operability (ACM 03735, 08248, 03403, 03402)
- 5 M8'Y2
- Technical Specification restriction to prevent the use j
7y of both stendby gas trains when venting the drywell vees 4442 set:ss os ca, eUse of a dedicated operator while venting the drywell es sa43 via SGTS ran*
eD,ew down ti,ne criteria /iesting during a LNP so uni:ss 3141 Verify resolution of ATWS issues, lack of LCO and SPO (1)
Acn m, tuming off the ATWS system to perform bettery
_ 7g voltage adjustments 41 Len:so se Verify resolution of IPEEE welkdown issues DRS/S eDetermine the need for the licensee to complete the P0(L)
-sa Aca:Mt.e?.
Verify implementation of setpoint changes identified by DRS Q'"1 *'7*
the setpoint verificwtlon program
. incorrect Rps.et,oints eYorw.;,ys 7" Error Low Low Water Level Calculation es Verify HELS,wooram completion DRS f
7 Movised 7/18/g7 1
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REFERENCE MILLSTONE UNIT 1 INSPECTION ITEM RESP STATUS 64 Verify drywell temperature profile, DRS PDCR completion and closeout necessary to update the plant t 'lign basis 65 unts3 24 04 Fire Protection / Appendix R Programs DRS artss oot 03
- Review fire detection and suppression system code compliance lasues resolution e Appendix R equipment, test, maintenance program, and surveillance program 88 Review commitment modification program for startup SPO (l) issues 67 ACR:M1.ss-Core reload DRS
$' 87*
- Error in LOCA model input data for GE11 fuel eSIL 581 eThe LOCA results are expectt,d to reduce the operating margin for MAPLHGR below the normal value (10%)
e3D monicore heat balance error correction
- Review reload 15/ core design for cycle 16 including the PDCR, safety evaluation and reload report.
as Core spray suction valves receives a sealin occident SPO (1) signal and can not be shut for leak isolation during an accident es SD valves (1, 2A,28) may not close under HELB SPD (1) conditions if open with greater than 300 degrees Rx water temperature 70 Review relief valve reliability DRS ACR trend 71 10 CFR 50.59 Process SPO Modifications installed prior to NRC approval and (L) sometimes before the TSAR submitted. (shutdown cooling, SRVs) 72 AcR: s264 isolation condenser thermal shock operability / service DRS life issue 73 Lenker fuel bundle root cause SPO (1) 74 W: 96-07 CRD scram solenoid pilot valve elastomer degradation SPO (I) 8 Revised 7/16/97
\\
N
of REFERENCE MILLSTONE UNIT 1 INSPECTION ITEM RESP STATUS 76 eel:96 09 08 Service water inspection (GL8913)
DRS Update o$o',j0'[,7',
e Arcor issue resolution IR:97 02 0
ACR:Mt 96. '
- SW and ESW system operability
- oest, eLPCI system operability 02372.M196-t oss, 7s ACR s250,Mt.
Electrical separation DRS/S
$0,33' eRx high level trip powered from the same source PO (L)
,,14 02 LER: 96 25 eCable Seperstion in Switchgear PIR:96 048 ACR:M196 os69,M1 97 0144 LER: 96 30 77 ACR:M196 Seismic concern with 4KV breaker racked out SPO (l) osos LER: 96 67 7s ACR: 07464 IGSCC Program weaknesses DRS LER: 9614,9N 2s,96 35 L11: 94 09 06 UR:;96 oos.
03.96 006 02 7s ACR:7304 Review f ailure to meet technical specifications root SPO (I)
[,'g 95 31 cause and corrective actions o2 Numerous LERs so ACR:M1 96-Review TRM for technical specification interpretations SPO (l) 1011 eMethod to track conditional LCO's et uni:90oot 02 Seismic qualification of FWCl valve air supply SPO (l) s2 URt:90-oot os FWCl test results SPO (l) ss URt:91 ost 04 Availability of short circult/ voltage drop celes DRS e4 vio:96-oo7 01 Control room habitability SPO
- Use of SCBAs (1)/SPO (L) as URI:95 02s 02 Refueling evolutions contrary to design basis SPO (l) 98 Vio:85 03102 Cross connecting 480V safety related buses SPO (I) 9 Movised 7/16/97 i
l
REPSRENCE MILLSTONE UNIT 1 INSPECTNHd ITSM RESP STATUS 87 untM 00641 Drywell fire / Technical Specifications vblation SPO (1)
LOR: M441, M 043 l
es Lan: so-00s Nonconservative ATWS low low water level setpoint SPO (l)
M L8#: 4 016 Recire pomp flow mismatch sury not perf in SPO (1) l accordance whh TS J
so Lan: M4:4 Temporary Modification to the scram air header SPO II) pressure switch instrument not removed g
81 L8R: # 082 Unqualified components in drywell preclude long term SPO II) operability 1
92 Lam: es43s Potential to bypass turbine stop valve when required to SPO (1) be operable I
88 L8R: #487 Automatic depressurization system may not be single SPO (1) fsilure proof I
- 4 LIR: **428.
Inservice inspection / Inservice Testing Programs DRS i
96 039 ACR: M197 cars,0400 es Lem: es44s LPCI sys inop due to stuck open injection check valve SPO (1)
ACR: M196 I
Ooes.co07 i
es Lem: es ost.
LOCA concurrent with LNP loss DC power prevents SPO (1)
"',$.,87[
closure of LPCI torus cooling valve I
- RWCU Valves oo4 3, u g.,s.
2 osso e7 unts6.e101 NCR Program ineffective SPO (l) stLM co604 SPO ACA:M196 (O) 04s4 2
es in:M 13 Operator Lloonsing and Training DRS uneM 01.s74143 eLOIT/ LOUT program requirement discrepancies ACR:M1.u.
1024.1025 M147
-0117.0148, 0100,0223,.
0269, OSH, 0437 MC 08s0 -
C.3.1.e C.3 3.c 10 nevised 7/1s/97 i
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P.YFERENCE MILLSTONE UNIT 1 INSPECTION ITEM RESP es Ett96 ot 01 Inoperable Gas Turbine Fuel Pump SPO IP i
,/,
ttR:9610
, -#D fM }
h 100 ri:96 os 21 Material Condition Program l
MC 0350 C.4.f
,,( y.,,j,,,.,.,,..
101 LER: 96 53, Radiation Effluents Monitoring Program Review l OF!, f 96 64,96 65;
}
97 06 1
ACR: M196-1042,1060, to69,M1 97 0242,o424 SPO (l) 102 ACR:M197-EDG Air Start System Review 0424 Eti: 96 09 o7 LER: 96 56, 96 66,96 60 102 ACR: M197 Use of "Non O" parts in "O" applications SPO (l) 0292,02o7, o026; ACR:
M196 ios7 104 ACR: M1 s7-GT Air Start System Review SPO (1) c260 105 ACR: M1 s7-Single failure vulnerability of FWCl/APR historical SPO (1) 0277.07s4 f ailure to meet ECCS acceptance criteria 106 ACR: M197*
Containment isolation valves exceed allowable stroke SPO (1) c200 time 107 Review deferred restart items list (50.54 (f) Responsel SPO (l) 106 Quality Assurance and Oversight Program SPO (I)
NRR e
11 Revised 7/16/97 i
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ENCLOSURE 2 SIGNIFICANT ITEMS LIST - MILLSTONE UNIT 2 4
4 9
i
i s'
MILLSTONE MESTART ASSESSMENT PLAN ENCLOSURE (2)
)
i Millstone Unit 2 Sinnificant Itamn Llat The following is a list of the Millstone issues that, as a minimum, require an NRC inspection and evaluation prior to restart.
REFERENCE MILLSTONE UN!T 2 INSPECTION ITEM RESP STATUS 1
MC 0350 SECTION C.1.3, MANAGEMENT OVER$1GHT AND EFFECTIVENESS; SP0(l)
C.2.1, C.2.2.e.d e, LICENSEE STAFF SAFETY CULTURE C.3.1,e,b,c,d 2
MC 0350 SECTION C.1.1, 50.54(fi/ICAVP (PHASE l and 11)
SPO C.1.3, C.I.4.g, C.3.2. C.4.f; FSAR ADEQUACY FOR RESTART (0/1/L)
CONFIRMATORY ORDER 10 CFR 50.59 PROCESS DATED 08/14/96 CONFIGURATION MANAGEMENT / DESIGN CONTRUL PROCESS (PART OF 10 AVP PHASE il 3
MC 0350 SECTION C.1.1 AND DESIGN CONTROL PROCESS CHANGES TO ADDRESS SPOIO)
C.1.3; C.2.2.d; UN.T 1 ACR 7007 UNIT 1 ACR 7007; UNIT 2 ACR 8761 NUMEROUS EXAMPLES OF DRAWINGS NOT REFLECTING ACTUAL PLANT CONFIGURATION l
4 MC 0350 ITEM C.1.4.e, EMPLOYEE CONCERNS PROGRAM SPOIL)
C.2.2.b.o; CONFlRMATORY ORDER DATED OCTOBER 24,1996 S
MC 0350 SECTION C.1.1, CORRECTIVE ACTION PROGRAM EFFECTIVENESS SPO(l)
C.1.3, C.1.4.d 1, C.2.1, C.2.2.c.e, C.3.1.d.m; C.4.f; SELF ASSESSMENT PROGRAM IMPLEMENTATION AND 1R 96-04 & 08 EFFECTIVENESS; eel 336/96 20130 COMMITMENT TRACKING S
Mf.,0350 ITEMS C.2.2.d.
WORK PLANNING AND CONTROL:
PLANT MAINTENANCE PROGRAM EFFECTIVENESS; SIGNIFICANT HARDWARE ISSUES RESOLVED; MAINTENANCE SACKLOG MANAGED AND IMPACT ON OPERATION ASSESSED; SURVEILLANCE TESTING: PLANT HOUSEKEEPING 7
MC 0350 ITEMS C.1.3.f, SYPASS JUMPERS, OPERATOR WORK AROUNDS &
SPO(1),
C.2.1.e C.3.2.e C 4.f,1; CONTROL BOARD DEFICIENCIES OSTl Revised 7/16/97
REFERENCE MILLSTONE UNIT 2 INSPECTION ITEM RESP STATUS 8
MC 0350 ITEMS C.2.1.b, PROCEDURE ADEQUACY) PROCEDURE UPGRADE SPoll)
OSTI C.2.2.d C.3.1.k. C.3.3.e,f; PROGRAM IFl 336/95 20103; PROCEDURE CLASSIFICATION. GENERAL USE VERSUS CONTINUOUS USE URI 336/96 0104; LOSS OF DC SUS EVENT ESTA8USH PROCEDURES REQUIRED BY TECHNICAL SPECIFICATION 6.8.1 URI 336/96 06 08 SHUTDOWN COOLING SYSTEM WATER HAMMER; NU LETTEM 816257 REVIEW OPERATING PROCEDURES TO PRECLUDE WATER HAMMER EVENTS IR 336/97 02; eel 97 0212 SURVEILLANCE PROCEDURE ADEQUACY SPO(O) 9 MC 0350 ITEMS C,1.4.g.
OPERATING PROCEDURES CONSISTENT WITH FSAR SPO(O) eel 96 C.2.2.g. C.3.3.e.f; DESCRIPTION OF SYSTEM OPERATION 06 UPDATED eel 336/96 0813.
eel 336/96 06-05, ADEQUACY OF PROCEDURE CHANGE PROCESS TO IM 97 02 eel 336/96-08 06, ENSURE OPERATION IN ACCORDANCE WITH UCENSE LER 336/97 02; ACR 11104 10 MC 0350 ITEMS C.2.1.g.
PROGRESS OF EMERGENCY OPERATING PROCEDURE ORS C.3.3.e.f; UPGRADES; (OU IR 336/95 21 ACCEPTABILITY OF DEFERRING ABNORMAL OPERATING PROCEDURE UPGRADES 11 MC 0350 ITEMS C.1.4.e,b,c, QUAUTY ASSURANCE AND OVERSIGHT PROGRAM spoil)
NRR C.2.1.c 12 MC 0350 SECTION C.1.1 UCENSEE RESTART PUNCH UST. REVIEW OF ITEMS SPO(!)
C.1.3, C.1.4.e, C.2.1.f g, DEFERRED UNTIL AFTER RESTART C.4.f,1 13 MC 0350 ITEMS C.3.1.g.h,l.),1 UCENSED OPERATOR STAFFING; CONTROL ROOM SPG(1)
C.3.3.e.b.d.g FORMAUTY; ATTENTIVENESS TO DUTY; ATTENTION TO OSTI DETAIL; OFF HOUR PLANT STAFFING; OVERTIME USAGE; AWARENESS TO PLANT SECURITY; AWARENESS OF EQUIPMENT STATUS; LOG KEEPING PRACTICES:
14 MC 0350 ITEMS C.3.1.e.
OPERATOR UCENSING AND TRAINING ORS C.3.3.c; (OU CONFlRMATORY ACTION ADEOUACY OF UCENSED OPERATOR TRAINING LETTER DATED MARCH 7, PROGRAM 1997; URI 336/97 0103 2
Revised 7/16/97
(
r l.*
MEFERENCE MILLSTONE UdIT 2 INSPECTION ITSM RESP SYATUS 16 MC 0350 ITEMS AUGMENTED INSPECTION COVERAGE DURING RESTART SPO(l)
NOTE 1 C.4.s.b.c,d,e,g INSPECTION: OPERABILITY OF TECHNICAL OSTI SPECIFICATION SYSTEMS; OPERAtluTY OF SECONDARY AND GUPPORT SYSTEMS; SYSTEM UNEUPS; RESULTS OF PRE STARTUP TESTING: POWER ASCENSION TESTING 16 MC 0350 ITEMS C.2.2 9 h, EMERGENCY PREPAREDNESS PROGRAM (INCLUDING DRS(EP)
C.3.1.m C.3.2.h; ORGANIZATION / STAFFING / DOSE ASSESSMENT NU LETTER (B16195) DATED CAPA81UTY)
FEBRUARY 10,1997 17 MC 0360 SECTION C.6 AND DISPOSITION OF REGULATORY ISSUES: UCENSE
- NPR, C.6 AMENDMENTS: EXEMPTIONS; REUEFS; ORDERS; SPO(U, SIGNIFICANT ENFORCEMENT ISSUES; ALLEGATIONS; OE, 01, AND 10 CFR 2.206 PETITIONS. COORDINATION WITH
- DRS, INTERESTED AGENCIES AND PARTIES.
OPA 18 ACRs 02621, M2 96 0239 MATERIAL, EQUIPMENT AND PARTS UST (MEPU
- NRR, eel 336/96 20142 & 43 PROGRAM DRS (SEB) 19 ACRs M2 96 0516 & 07958; EQUIPMENT ENVIRONMENTAL QUALIFICATION (EEQ)
ORS eel 336/96 0512, PROGRAM (EEB) eel 336/96 20120, URI 336/G319 02 HIGH ENERGY UNE BREAK PROGRAM 20 IFl 336/95 0101 MOTOR OPERATED VALVES (GL 8910)
DRS (SEB) eel 336/96-0511 INACCURATE INFOr.MATION PROVIDED TO THE NRC REGARDING GENERIC LETTER 8910; eel 336/96 06 0S DYNAMIC TESTING OF AFW TERRY TUR81NE STEAM ADMISSION MOV; eel 336/95 06 01,03 & 04 PRESSURE LOCKING OF CONTAINMENT SUMP RECIRCULATION VALVES 21 MC 0350 ITEM C.3.3.o; FIRE PROTECTION / APPENDIX R PROGRAMS DRS IR 336/96 08; (EEB)
UCENSEE SELF-ASSESSMENTS APPENDIX R RELATED ABNORMAL OPERATING AND QA AUDITS; PROCEDURES; ACR M2 96-0460 APPENOlX R COMPLIANCE ASSOCIATED WITH THERMO-LAG 22 ACRs h'.2 96-0613; CONTAINMENT SUMP SCREEN MESH SIZE & ECCS PUMP DRS eel 336/96 06-10 & 11 THROTTLE VALVE CLOGGING (SEB) 3 Revised 7/16/97
MEFERENCE MILLSTONE UNIT 2 INSPECTION ITEM RESP STATUS 23 ACRs 01991. M2 96 0449, HYDROGEN MONITORS AND POST. ACCIDENT SAMPLING
$ Poll) 0467, 0654, 0655, & 0656:
SYSTEM INOPERABLE AND FAILURE TO MEET DESIGN eel 336/96 0811,12 & 13, SASIS AND LICENSING BASIS eel 336/96 20103 & 41, URI 336/96 0105 24 ACRs 08174,04047,06372 &
EXCESSIVE REACTOR COOLANT SYSTEM HEATUP AND SPO(l) 09739; COOLDOWN RATES: EVALUATION OF SIMULTANEOUS URI 336/95 42 03 REACTOR COOLANT PUMP AND SHUTDOWN COOUNG SYSTEM OPERATION 25 NUMEROUS ACRs:
ECCS PUMPS SUCTION LINE FROM RWST HAS DRS r
URI 336/96-06 08 NUMEROUS DEGRADED OR INOPERABLE PIPE SUPPORTS, (CMME)
MANY CAUSED BY WATER HAMMER 26 ACR 112521
'8' EMERGENCY DIESEL GENERATOR FAILURE.
$ Poll)
UPDATED eel 336/96 0910 INADEQUATE CORRECTIVE ACTIONS IR 97 02 27 eel 336/96 20109 INADEQUATE DESIGN CONTROL MEASURES FOR SPO(O)
VERIFYlNG ACCURACY OF INFORMATION CONTAINED IN DESIGN BASIS DOCUMENT PACKAGES l
28 eel 336/96 201 11, FAILURE TO ADEQUATELY CONTROL INSTALLATION OF SPO(l) eel 336/96 20131 TEMPORARY MODIFICATION TO THE RBCCW SURGE TANK 29 eel 336/96 201 12 SEPARATION AND SINGLE FAILURE CONCERNS FOR WIDE SPO(I)
MANGE NUCLEAR INSTRUMENTS 30 eel 336/96 20126 FAILURE TO IMPLEMENT CORRECTIVE ACTIONS SPO(l)
CONCERNING ' DUAL FUNCTION
- ISOLATION VALVES 31 eel 336/96 20128 FAILURE TO ADDRESS STATION BLACKOUT ISSUES SPoll)
IDENTIFIED IN THE VECTRA ASSESSMENT 32 eel 336/96 20129 FAILURE TO IMPLEMENT CORRECTIVE ACTIONS FOR SPO(l)
UPDATED l
AUDIT ISSUES INVOLVING TRENDING AND IR 97 02 PRIORITIZATION OF NON-CONFORMANCE REPORTS 33 eel 336/96 20136 INADEQUATE CORRECTIVE ACTION CONCERNING A DRS SEISMIC DESIGN DEFICIENCY OF A VITAL SWITCHGEAR (CMME)
ROOM COOLER g
4 Revised 7/16/97 I
o
)
REFERENCE MILLSTONE UNIT 2 INSPECTION ITEM RESP
$TATUS 34 eel 336/96 08 06 IMPLEMENTATION OF CORRECTIVE ACTION OF SPO(l)
UPDATED CHANGING OPERATING PROCEDURE TO LOCK OPEN IR f 7 02 REFUELING POOL DRAIN VALVES, AS SPECIFIED IN THE FSAR, WAS INADEOUATE 35 eel 336/96 08 08 INADEOUATE CORRECTIVE ACTION IN LER 336/96 24 SPoll) 36 eel 336/96-0810 INADEOUATE CORRECTIVE ACTIONS TO ADDRESS UNIT SPoll)
UPDATED 1 HEAVY LOADS UFTED OVER THE UNIT 2 VITAL IR 97 02
)
SWITCHGEAR ROOM 37 eel 336/95 44 05 ICE BLOCKAGE OF SERVICE WATER STRAINER SPoll)
BACKWASH LINE 38 URI 336/96-0511 (IFS NO. URI SPENT FUEL POOL FSAR UPDATES SPoll)
CLOSED IR 97 02 336/96 05 17) 39 eel 336/96 0410 ERRONEOUS RBCCW FLOW VALUES IN CONTAINMENT DRS TEMPERATURE PROFILE ANALYSIS (SE8)
URI 336/96 20138 FAILURE TO CONSIDER POST ACCIDENT FLUID TEMPERATURE IN HPSI FLOW EVALUATION 40 LER 336/96 31 POTENTIAL STEAM GENERATOR OVERPRESSURE DUE TO DRS RESTRICTIVE MAIN STEAM SAFETY PIPING (SEB) 41 ACM M2 97 0023 SEIMANS COMPUTER MODEL OF REACTOR CORE LARGE NMR AND SMALL BREAK LOSS OF COOLANT ACCIDENTS 42 IR 336/94 201 (IFS NO IFl EMERGENCY DIESEL GENERATOR FUEL DAY TANK DOES SPO(U 336/94 201 90)
NOT SATISFY 7 DAY DESIGN BASIS CAPACITY 43 URI 336/96 0814 INAPPROPRIATE REMOVAL OF STARTUP RATE TRIP SPO(l)
LER 336/96 29 44 ACR 02797, ACR 09563, POTENTIAL TO EXCEED CONTAINMENT DESIGN SPO(l)
ACR M2 96 0153; PRESSURE FOLLOWING A MAIN STEAM UNE BREAK LER 336/97 06 45 ACM M2 96 0296 FAILURE OF MAIN STEAM CHECK VALVE FOLLOWING A SPol MAIN STEAM UNE BREAK (MSLB) COULD CAUSE WOTH STEAM GENERATORS TO BLOW DOWN RESULTING IN EXCEEDING CONTAINMENT DESIGN PRESSURE THE UCENSEE'S MEPL PROGRAM DESIGNATES THE MS CHECK VALVES AS NON-QA WHICH THE LICENSEE HAS EVALUATED AS ACCEPTABLE.
5 Revised 7/16/97
', I RESP STATUS l
MILLSTONS UNIT S INSPECTION ITSM R9PSRSNCE SPOll)
CONTROL ROOM AIR CONDITIONING COMMON INLET de LER 334/97 02 DAMPER COULD BECOME STUCK CLOSED, DISASLING l
DOTH FACILITIES. DAMMR HAS NO MANUAL OPERATOR AS ST ATED IN FSAR.
E SP0(l)
REACTOR PROTECTION SYSTEM AND ENotNEERED 47 URI 334/96-08 09 SAFETY FEATURE RESPONSE TIME TESTING LER 336/96 24 i
TECHNICAL SPECIFICAfl0N LIMITS FOR INOPERASLE SPO(l) 46 ACM M2 96 0842 MAIN STEAM SAFETY VALVES NON CONSERVATIVE I
49 LER 334/96 30, LER 336/97 06 INSERVICE INSPECTION /INSERWCE TESTING PR00 RAMS ORS (SESI CR M2 97 0491 & 1229 SP0(l)
CONTROL /USE OF VENDOR INFORMATION SO SERVICE % ATER SYSTEM OPERATIOfJA'. PERFORMANCE ORS St IR 338/95 29 (SES)
INSPECT:0N (SWSOPI) FOLLOWUP Note 1: Since thie inspection will occur followin9 toetort approval, the closure of thle 6ttm will not be reflected het.
)
6 RevlSed 7/16/97
\\
ENCLOSURE 3 SIGNIFICANT ITEMS LIST - MILLSTONE UNIT 3 y
s 8
s l *.-
MILLSTONE RESTART ASSESSMENT PLAN ENCLOSURE (3)
Millstone Unit 3 Sinnificant items Lis.1 REFERENCE MILLSTONE UNIT 3 INSPECTION ITEM RESP STATUS 1
ACR: 10773 RSS AND QS$ PIPING TEMPERATURE NRR Update eel: M4613 MAYSE HIGHER THAN ANALYZED (NRR REVIEW ENG.
DRS ORM46 LER: M407 ANALYSIS, DRS INSPECT INSTALLATION)
SPO (0) 01 & 02 3
2 eel: M 201 FSAR ADEQUACY FOR RESTART SP0(L) 01 3
ACR: 08715 REACTOR POWER INCREASE WHEN UNDORATED CATION DRP CLOSED DEMlH PLACED INTO SERVICE SCHS DEMIN2 1RM40 4
ACR: 01896 EDO SEQUENCER CDA SIGNAL OUTPUT "A" TRAIN DRS CLOSED COMPONENTS STARTED IRM49 8
ACR: 01844 FAILURE TO ENTER AN ACTION STATEMENT WHEN MSIVS SP0(l)
Update IR VIO: 94 34 WERE Ci OSED. (TECH SPEC AMEND) 9742 01; LER:97 00 S
ACR: 04168 RCP SEAL INJECTION FILTER "S" GASKET FAILED RESULTING DRP CLOSED IN SPILL OF COOLANT TO FLOOR DRAINS BRM48 T
ACR: 08092 RCS CHECK VALVE SODY TO SONNZ! LEAK; 3 RCS*Viet DRP CLOSED IRM48 8
ACR: 01635 WHILE DEWATERING SPENT RESIN, THE WASTk DRP CLOSED TEMPERATURE IN THE LINER RAISED FROM 90 TO 310'F IRM46 9
ACR: 10643 NEED FOR ADDITIONAL REYlEW OF RESPONSE TIME TESTING SPO(f)
FOR PROCEDU,4ES 10 ACR: 11322 CLOSURE OF PIR WITHOUT ADDRETSING DEllGN FEATURE DRP CLOSED OF AFFECTED COMPONENTS 1RM49 11 NULTR TURBlNE DRIVEN AUX FEEDWATER DESIGN CONCERNS.
SPO(1)
(016397)
(TECH SPEC AMEND.)
1111/95, ACR: 10774 S10780 eel: M 201 04, Os; URI:
M 20140 Revised 7/16/97
...~... ~.~ -.
t al
=
REFERENCE INLLSTONE UNIT 3 INCPECTIONITEM RESP STATUS l
-it ACR:974317 CONTAINetENT FOUNDATIDN BROS 40N I
SPO (L) 4323 t
URI: 9644 i
it, MM14, e6
- 16 IPl: 641140 IN: 9711
)
is ACR:M 4M, CCP SYS7800 OPERATION ADOVE DESNBN TEtePERATURE: 3 SP0(l)
Update iM27,M.
RMS*HCV 406407 FAILMS OPEN; AND OTHER Fail.URE 4000E8 RM40 j
eM7 i
URI: M46 l
M;lR: M 30(
LER: M.M &
t 9640 14 ACR: 7746 SOCS OPERATIONAL CONF 100RAtl0N CONTROL (TECH SPEC SP0(f)
Update R
[
9742 j
URI: M4147 ATTEND.)
16 ACR:M 41M LETDOWN HEAT EXCHANGER LEAKAGE AND DES 60N SP0(l)
Update OR9646 l
581: M4616 DISCREPANCIES l
16 Uniti DUAL PUNCTION VALVE CONTROL AND TESTWO SPO (1)
Updete IR i
9742
[
ACR: 01936 17 ACR: 73M RCP SEAL HOUSING LEAKAGE AND DOLT CORROSION DRS t
it ACR: 10M2, CONTROUUSE OF VENDOR INFORbtATION DRS UPdete SP0(l)
R 9742 PPR O.3 eel: M401 it,M 301 18, M401 19 U Rl: M 4 01 17 it Ulti:M 401 RESOLUTION OF APW VALVES HELA CONCERN SP0(l) 16 M
Vlo:M4613 EttPLOYEE CONCERNS Pft00 RAM SP0(L) 0000800 873008 i
C 1.4.e S C.n.s.6 21 FAft0UE CYCLE OPEN 873005 F 87790 DRS CLOSED IR0641 (UNIT IISSUE) 7 at PART 70 STORAGE AND llWENTORY IP 847M (UNIT 1 ISSUE) -
DRS CLOSED ino646 33 PORetALfiY OF NON ft0UTINE SECUltlTY ACTfVITIES AND NEW DRS CLOSED PUEL SECURfTV IP Sitto IR9646 2
Revised 7/16/97 L
)
-_._______...___.._-,__,-...._..-.,.__...._.__.._..-...~,.._.......,--..m...
-, _ -. - ~.. _ -...., _ ~. _ -... _. _..---
Y
.O STATUS l REFERENCE MILLSTONE UNIT 31NSPECT10N ITEM RESP 24 URI: 9s4144 OVERLAP TESTING OF RPS/ESF SP0(l)
Update LER: 9717 IRC741 26 ACR: 912 MATERIAL EQUIPMENT AND PARTS List (MEPL) PROGRAM DRS UPdete URl: 984710 SP0(l)
IR M.201 eel: M.201 87*202 43 M
ACR: M.277, MOTOR OPERATED VALVES (OL 8910)
DRS 0218,627, 12H2 LER: M.
it,N,M.36:
URI: 961749 IFl: 964141, 961741,02, 03, N, M;6N:
9747 27 PPRO1.C, MISSED SURVEILLANCESITEST CONTROL SP0(I)
CLOSED O.2 MC 0360 BRH48 ITEMS C.4.e to PPR 0,1.C DILUT60N EVENTS SPO(I)
CLOSED RM40 29 PPR O.1.C FEEDWATER HAMMER DRS CLOSED RM41 20 IR: 96 31, NU AFW CHECK VALVE LEAKAGE SP0(l)
CLOSED LTR (815397)
R:0742 11/1/98 PPR G.1.C, ACR M4868 31 PPRG1.C.
WORK.AROUNDS AND ASUSE OF USE.AS48 DEFICIENCIES SPO(l) 0.2 MCOMO ITEMS C.1.3.f.
C.2.1.e C.3.2.e, C.4.f.&I 82 NOV M.18 WORK PLANNING AND CONTROL DRS M
PPR 0.2 RAC O M O ITEMS C.2J.e C.4.f,h,I 3
Revised 7/16/97
RESP STATU0 REFERENCE MILLSTONE Uhlt 3 INSPECTION ITEM DR8 33 IR: M.Mi SEISMIC M PPRG.2 LER: M403; ACR: M.
DMSI CR: 97 06H EFFLUENT / ENVIRONMENTAL SAMPLING AND ANALYT) CAL DRS Update M
IP:547M;
- 1RM49, VIO: M46 PROFICIENCY M.13 10;lFl:M.13 01 DRS Update 35 IP:M7M RADWASTE SYSTEMS / CONTROLS IRM48 DRS M
ACR:M3 97 HEAT EXCHANGER PERFORMANCh (GL 4913)
Osts 37 IR M 44 CORRECTIVE ACTION PROGRAM EFFECTIVENESS (TECH SPEC SPO(l)
Update IR 87*
eel: M.201 AMEND.)
02,97 202 13,21,22,23, 24,26,27,28, 29 MC 03M ITEMS C.1.1, C.1.3, C.1.4.d e S.
C.I.1, C.2.2.c.e.
C.3.1.d. C.4.f St REVIEW 0737 ACTION ITEMS FOR COMPLETION SPO(l)
DRS 39 MC 0360 REVIEW ENGINEERING SACKLOGS 08T1 ITEMS C.3.2.e c 40 MC03H REVIEW 60.84F ISSUES FOR RESTART / REVIEW DEFFERED SPO (L)
Update ITEMS C.1.1, RESTART ITEMS LIST SPO(I) 1RM 06, 97 202 C.1.3, C.1.f,&
9.
C.4.f,1 41 ACR: 7007 REVIEW SELF ASSRSSMENT ROOT CAUSES AND VERIFY SPO(l)
Update IR: 97 02 URI: SS4141 CORRECTIVE ACTIONS (IP40800)
VIO: M4944 MC 0380 C.1.4.1 42 IR: M48 FIRE PROTECTIONIAPPENDtX R PROOMMS DRS Update IR:97 202 43 ORDER M.84(fylCAVP (PHASE I and II)
SPCNO) 4 Revised 7/16/97
O'
,.o LICENSING ISSUES REQUIRED FOR RESTART MILLSTONE UNIT 1 No.
TAC No.
Issue Status 1
M94258 Standby Gas Treatment System Welting for RAI response.
Licensee may revise significantly.
2 M99062 Safety / Relief Velve Electrical Design Welting for RAl response.
Modification 3
M97934 Response Time Testing Under staff review.
Clarification / Modification 4
M98833 Neutron Monitoring Under staff review.
Note: The licensee Indicated that et least one additional licensing action will be needed prior to restert.
Revised 7/16/97
\\,
I t
LICEfjSING ISSUES P.EQUIRED FOR RESTART *
- MILLSTONE UNIT 2 i
No.
TAC No, issue Status 1
M97748 Met. fewer inst.
Under Re,vieg 2
fA98277 Ultimate Heat Sink UnderRevkw 3
M98374 Enclosure Sullding Under Review 4
MS4823 Cont isolation Velves Need Additionalinfo.
-g 5
M92879 Cont. Mm. Emer. Vent System Under Moview i
1 8
M97880 EDG Fuel Oil. TS Scals Change Submit 08/15/97 7
ESFAS Hersh Environment Submh 08/31/97 8
MCS P.T Curves Submit 08/15/97 8
Max. Containment Pressure Limit submit 08/15/97 10 Tech. Spec. Verbatim Compliance Submit 08/15/97 11' M94105 Steam Gen. Slowdown Mont, Under Review 12' Rx Trip Setpoints SG Safety Velves Submit TSD 13' Tech. Spec. Safety Limit Curves Submit TSD 14 M97880 Siemens LOCA Anal. Evolustion (non TS)
Under Review l
15 Startup Mete Trl,s (non TS)
Under Review
- These home are eweiting vendor snelvels to determine if they are restert items.
- 13 emendment requests (8 under review & 7 to be submitted),2 licensing activitse requiring review and approval.
l I
2 Revised 7/18/97
I LICENSING ISSUES REQUMED FOR RESTART MILL STONE UNIT 3 No.
TAC No.
Issue Status 1
M92798 Modified M81V surveillence end action statements.
Amendment No.138 lesued 4/10/97 2
M95489 Modified the description of the time constants Amendment No.134 associated with the OT and OP Dette T calculations, issued 3/10/97 3
M98288 Chen9ed AFW motor and turbine driven pump Amendment No.139 surveillences.
Issued 5/29/97 4
M98289 Separated the required testin9 of MOV thermal Amendment No.140 overload protection into 2 new surveillances issued 5/29/97 5
M98415 Cranged the RHR suction relief volve setpoint.
Amendment No.143 leshed 7/10/97 8
M38455 CMfied the actions to be taken when an area Amendment No.141 temperature exceeds the limit.
Issued 8/24/97 i
7 M98458 chen9ed the surveillence requirements for the Amendment No.142 hydrogen monitors, lesued 8/24/97 8
M98525 Chrnges Charging and 81 pump surveillances.
Under staff review.
I 9
M98630 Ad:is valves that must be closed to provide flood Under staff review, protection.
10 M98878 Overcurrent protection devises. Relocates the Under staff review.
300% and 150% oircuit breaker test currents to the Bases.
11 M98879 leeue clarifies the number of bettery banks required Under staff review.
In Modes 5 & 6.
12 M98880 issue addressa.s seismic qualification of the spent Under staff review, fuel rocks.
13 M988C1 lesue corrects the wordin9 sesociated with ventin9 Under staff review, the charging pumps.
14 M98899 Will allow the SMM to be operable at a lower count Under staff review, rete.
18 M98724 Revises the bettery chen9er test requirements to Under staff review.
equel to or greater than 132V.
18 M98888 leave addreseos the testing of the RSS pumps.
Under staff review.
17 M99018 Creates e servoinance for the attuation when the Under staff review.
resetor trip breakers are closed.
3 Revised 7/18/97
No.
TAC No.
Issue Status 18 M99041 Table 2.21 Notes. Defines the terms.
Under staff review.
19 M99042 Revises the regulfed volume in the DWST and CST.
Under staff review.
f 20 M99131 leeue involves partial. and full stroking MSIVs.
Under staff review.
21 M99132 losue involves manuel containment isolation velves Under staff review, that require intermittent operation in Modes 14.
22 M99261 lesue involve 6 adding a new TS and Bases for the Under staff review.
SGAR8Vs.
Note: The licensee has indicat.4 that it plans to submit 4 edditional licensing issues whleh will be needed prior to restert.
4 Revised 7/16/97
a---
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6 i
ENCLOSURE 4 4
MC-0350 - RESTART APPROVAL CHECKLIST ALL MILLSTONE UNITS i
1 9
.e,n-r-,-,-
e
-.ma, e
. _.... ~ _. - _ _. _ _ _
i
,(
l l
i o.
REPERENCE ANLLSTONE UNIT 3 WSPECTON ITsu RESP STATUS TO URi! M 48 14 REVIEW TRM POR TSCN. SPEC. INTERPRETATIONS: EVALUATE DRS update LER: Meta.
TS AND OPER. UCENSE SSUES R:9742 S1, M 37, M.
4 M. M42, M.
l 43,M44 M.
41,t?44,97 97.97 18,97 it 5
71 84C SSM REVIEW UCENSEE EVENT REPORTS FOR RESTART m3088 SPOM
[
t C.1,4.1 72 REWEW ENPORCtt4ENT AND UNRESOLVED ITEAAS POR ITSMS SP0(l) i a
POR RESTART 280E8 l
73 NOW9646 OUAUTY ASSURANCE AND OVERSONT PROGRAM OSTI l
it;IPl:M48 49800 if IIC 9380 C.1.4.a,b,s, l
C.S.1.s 74 URl: 9646 WSERVICE INSPECTION /INStRVICE TESTING PROGRAMS DRS Update i
it; LER: M.
R:87*
til CR 9y, 92,97 392 901 i
rs Irl: 964s.1s, TiA 28UE8 (s00 ExNAUST a REQUIREO e Or SW PUMPS)
- R M4e.17 SPO(u t
to Ort: Osas.17 CRACKWO OF PUSE PERRULES DRS CLOSE0 m:97 302 l
77 IFl: 964446 POTENTIAL FREE 2WO OF SW BACKWASN LWES SP0(1)
Update R:M40 76-URI:9847 it CPR 90.99 PROCESS SP0(Q 97, Eti: M 301 St. M, 96,6e, M,98 l
79 Sti: 96 301 CONPOURATION MANAGE 40ENTfDESON CONTROL PROCESS SP0(l)
Update 99, is, M, 37, SP0(0) m:9742 se (PART OFICAVP PHASE I) tsC Sato C.S.I.f 5
7 Revised 7/16/97
l
).l
.I 4
REFERENCE INLLSTONE UNIT 3 INSPECTION fTEM RESP STATM i
09 ACR: 97.M8 PROCEDURE ADEQUACY / PROCEDURE UPGRADE PROGRAM SP00)
Update OSTI R9741 bel: M 301, 4
18,it l
MC 0300 1
C.1.1.b, CJ.R.d.
C.S.1.k.
C.3.3.e f Das uPaM i
ei Em: M.M1 mTwo or wmmTEm IR:9742 j
Ll St.33 Mi LER: M 32 1
32 eel: M.301 QUAUTY ASSURANCE RECORDS SPop)
I to 83 NU LETTER EMERGENCY PREPAREDNESS PROGRAM DRS Update IR:M 49, i
(819199),
2/10/97 DNCLUDINo ORGANIZATION /STAF>lNGADOSE ASSESSMENT 97 202 l
i MC 0300 CAPABILITY)
ITEMS C.I.2.g. h.
C.3.1.m.
C.3.2.h:IFl:
M4641 M
MC OSSO SECURfTYISSUES.CORRECTWE ACTION DRS j
fTEM C.3.1.1 eel: M4618, a
9741.XX U1 j
VIO: M49 20 SS ACR: M4M, OTHER RSS AND RELATED DESIGN BASIS CONCERNS SPO (0) 407,420, NRR 1978,97 439, 4
iM,400 LaR: 9743, 97 18,97 21:
CR:071029 N
CAL:197 OPERATOR UCENSING AND TRAINING SP0(l)
Update 010; DRS 1R: 97-CR:97 202,97-0927 04 8
Revised 7/16/97
+
t e
i l
P
)
i ENCLOSURE 5 i
LICENSING AMENDMENT REQUESTS f
1
'k e
P I
..n-
-g.
c--,An-..r...-
,n-..,,
l 4
l lNEED l STATUS l RESP I ASSESSMENT OF COMPLIANCE WITH REGULATORY C.5 f1EQUIREMENTS a.
Applicable license amendments have been X
RAP issued.
b.
Applicable exemptions have been granted.
X RAP c.
Applicable reliefs have been granted.
v.
RAP d.
Impored Orders have been modified or X
RAP rescinded.
e.
Significant enforcement issues have been X
f.
Allegations have been appropriately addressed.
10 CFR 2.200 Petitions have been X
NRR appropriately addressed.
h.
Atomic Safety and Licensing Bond hearings NA have been completed.
C.6 COORDINATION WITH INTERESTED AGENCIES AND EARTIES Federal Emergency Management Agency X
_l b.
Environmental Protection Agency X
RAP c.
Department of Justice X
OE oi d.
Department of Labor X
OE e.
Appropriate State and local officials X
GLO f.
Appropriate public interest groups X
RAP g.
Local news medie X
OPA 15 Revised 7/16/97
=
NEED l STATUS l RESP c.
Understanding of management's expectations X
osTi 40500 and go,als.
d.
Understanding of plant issues and corrective X
osTI sR actions.
9 9 e.
Qualifications and training of the staff.
X osil 41500 l f.
Staff's fitness for riuty, NA g.
Attentiveness to duty.
X osTI i h.
Level of attention to detall.
X osil
!l.
Off hour plant staffing.
X SRI J.
Staff overtime usage.
X l SRI k.
Procedure usage / adherence.
Awareness of plant security.
X l DRs m.
Understanding of offsite emergency planning X
DRs issues.
I C.3.2 Annenament of Corocrate Suonort and Site Enoineerino Suonort X
osTl l s.
Corporate staff understanding of plant issues.
! b.
Corporate staff site specific knowledge.
X osTI c.
Effectiveness of the corporate / plant interface X
osTi meetings.
d.
Corporate involvement with plant activities.
X osTI e.
Effectiveness of site engineering support.
X ons OSTl f.
Effactiveness of the site design modification X
DRs osTI
- process, g.
Effactiveness of licensing support.
X RAP h.
Coordination with offsite emergency planning X
RAP officials.
I 1
13 Revised 7/16/97
\\
l
~
t I*:
NEED STATUS MEsP l
t C.3.3 operator lamuns l
a.-
Licensed operator staffing meets requirements and licensee goals.
X osit i
l b.
Level of formality in the control room.
X osTI sni c.
Effectiveness of control room simulator X
DRs i
- training, d.
Controi room / plant operator awareness of X
osTI-sal equipment status.
e.
Adequacy of plant operating procedures.
X SRI Ps f.
Procedure usage / adherence.
X SRI osti i
X iosTI g.
Lop keeping practices.
C4 ASSESSMENT OF PHYSICAL READINESS OF THE P1AhlI.
a.
Oparability of technical specification systems.
X nsis b.
Operability of required secondary and support X
osti systems.
c.
Results of pre startup testing.
X sPo osil a
d.
Adequacy of system lineups.
X osTi e.
Adequacy of surveillance tests / test program.
X osTi f.
Significant hardware issues resolved (i.e.
X osTi damaged equipment, equipment ageing, modifications).
g.
Adequacy of the power ascension testing X
osTi sni
- program, h.
Effectiveness of the plant maintenance X
osTi Das program.
I.
Maintenance backlog managed and impact X
osis on operation assessed.
J.
Adequacy of plant housekeeping and X
osTi l
equipment storage.
14 Revised 7/16/97
I'e l
l-l NEED l STATUS l RESP j C.1.4 Self Annessment Canability I
The occurrer.ce of an event may be indicative of potential weaP.nesses in the licensee's self assessms:,nt capability. A strong self assessment i
l capability c.estes an environment whcre problems are readily identified, prioritized, and tracked. Effective corrective sctions require problem toot cause identification, solutions to correct the cause, and verification methods thet ensure the issue is resolved.
Senior licensee management effectiv* ness in ensuring effective self assessment is treated st parately.
a.
Effectiveness of Quality Assurance Program.
X RAP 40500 b.
Effectiveness of Industry Experience Review X
OSTI i
Program.
l 40500 c.
Effectiveness of licensee's independent Review X
SRI osT Groups.
,g, d.
Effectiveness of deficiency reporting system.
X SRI OSTI 40500 e.
Staff willingness to raise concerns.
Effectiveness of PRA usage.
X osTi g.
Effectiveness of commitment tracking X
h.
Review applicable extemal audits X
osT 1.
Quality of 10 CFR 50.72 and 50.73 reports.
X SRI C.2.1 Mannaement Oversiaht and Effectivanama a.
Goals / expectations communicated to the staff.
X OSTI 40500 b.
Demonstrated expectation of dherence to X
SRI osTi procedures.
~
c.
Management involvement in self assessment X
RAP 40500 and independent self assessment capability 11 Revised 7/16/97 v
! NEED l STATUS l RESP d.
Effectiveness of management review X
sri committees.
,[n[h 8
Menehment's demonstrated awa.aness of X SRI e.
osTi day to day operational concerns, f.
Management's ability to identify and prioritize X
SRI significant issues.
[gs g.
Management's ability to coordinate resolution X
SRI osT of significant issues.
40500 h.
Management's ability to implement effective X
SRI osT corrective actions.
C.2.2 Manmaament suonort a.
Impact of any management reorganization.
X RAP 40500 b.
Effective and timely resolution of employee X
RAP J
concerns.
c.
Adequate engineering support as demonstrated X
! DRs i
by timely resolution of issues.
osTI d.
Adequate plant administrative procedures.
Effective information exchange with other X
SRI utilities.
osTI If.
Participation in industry groups.
NA 40500 g.
Effectiveness of Emergency Response X
DRs Organization, h.
Coordination with offsite emergency X
DRs l
planning officials.
l C.3.1 Amnessment of Staff RAP sai a.
Demonstrated commitment to achieving X
osTI improved performance, b.-
Demonstrated safety consciousness.
X osTi SRI 12 Revised 7/16/97 e
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y-,
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4' I
l
!NEED ! STATUS l RESP B.4.4 Obtain Commants 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 process when they contribute positively to the review. Note:
If needed, comments concerning the adequacy of state and local emergency planning and preparedness must be obtained from FEMA headquarters through NRR.
a.
Obtain public comments.
X IftNs item will not be renected on tNs list.
I st.o b.
Obtain comments from State and Local lX Officials (Region).
c.
Obtain comments from applicable X
RAP Federal agencies.
B.4.5 l Clomeout Actions When the actions to resolve the restart issues and significant concems are substantially complete, closeaut actions are needed to verify that planned inspections and verifications are complete. The licensee should certify that corrective actions required before restart are complete and that the plant is physically ready for restart. This section providas actions associated with completion of significant NRC ggp reviews and preparations for restart, oSTI a.
Evaluate licensee's restart readiness self-assessment.
X b.
NRC evaluation of applicable items from X
RAP Section C "lSSUES" complete.
7 Revised 7/16/97
I.
NEED ! STATUS l RESP c.
Restart issues closed.
Conduct NRC restart readiness team X
Osil inspection.
e.
Issue augmented restart coverage inspection X
osT plan.
f.
Comments from other parties considered.
X RAP g.
Determine that all conditions of the Order / CAL X
RAP are satisfied, h.
Re review of Generic Restart Checklist X
B.5 RESTART AUTHORIZATION fB.51 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 think l
broadly and ask: "Are all actions substantially complete? Have we overlooked any items?"
i Prepare restart recommendation document and a.
basis for restart.
X RAP b.
NRC Restart Panel recommends restart X
RAP c.
No restart objections from other applicable HQ X
McKee affices.
l d.
No restart objections from applicable Federal X
RAP agencies.
e.
DSPO concurs in restart recommendation X
DSPO j
f.
NRR Director concurs in restart X
DsPOt.
recommendation.
g.
EDO concurs in restart recommendation when X
EDO required.
X sPO Conduct ACRS briefing when requested (NRR).
h.
l.
Conduct Commission briefing when requested.
X l DSPO 8
Revised 7/16/97
4 g
f NEED STATUS l RESP J.
Commission approves in restart authorization.
X COMM i
k.
DSPO authorizes restart.
X EDO i
B6 RESTART AUTHORIZATION NOTIFICATION fB.8)
Notify the applicable parties of the restart authorization. Notifications should generally be made using a memorandum or other format consistent with the level of formality required. Communication of planned actions is important at this stage to ensure that NRC intentions are clearly understood, s.
Commissit,n (if the Commission did not concur in the Restart Authorization or as requested)
(NRR).
NA RAP b.
EDO (if the EDO did not concur in the restart NA EDO recommendation or as requested) (NRR).
c.
Congressional Affairs (RAP).
X OCA d.
ACRS (a briefing may be substituted for the X
sPO written notification if the ACRS requests a briefing) (NRR).
f e.
Applicable Federa! agencies.
X RAP lf.
Public Affairs.
X OPA
! g.
State and local officials.
X l SLO h.
Citizens or groups that expressed interest X
RAP during the restart approval process.
Root Cause Annenament C.1.1 a.
Conditions requiring the shutdown are clearly X
RAP understood, b.
Root causes of the conditions requiring the X
RAP shutdown are clearly understood, c.
Root causes of other significant problems are X
RAP clearly understoed.
d.
Effectiveness of the root cause analysis X
RAP program.
9 Revised 7/16/97
\\
L.,
l
!NEED l STATUS l RESF l
C.1.2 Damnae Assessment a.
Damage assessment was thorough and NA comprehensive.
j b.
Corrective actions clearly restored systems and NA equipment or verified they can perform as designed.
C.1.3 Corrective Actions Thoroughness of the corrective action plan X
RAP a.
b.
Completeness of corrective action programs X
SRI for specific root causes.
c.
Control of corrective action item tracking.
X SRI OSTI d.
Effective correct!ve actions for the conditions X
SRI oSTI requiring the shutdown have been implemented.
e.
Effective corrective actions for other significant X
SRI OSTI problems have been implemented.
f.
Control of long term corrective actions.
X SRI OSTI 40500 g.
Effectiveness of the corrective action X
SRI OSTI verification process.
40500 10 Revised 7/16/97
~
4 N
.2 o'
l l NEED l STATUS l RESF B.4.1 Root Causes and Corrective Actiona OSTI a.
Evaluate findings of the special team X
inspection.
b.
Licensee performs root cause analysis X
NU osTI and develops corrective action plan for toot causes.
c.
NRC evaluates licensee's root cause X
RAP osT1 determination and corrective action plan.
B.4.2 B.4.2 hrsament of Eauloment Damnos NA For events where equipment damage occurs, a thorough assessment of the extent of damage is necessary. A root cause determination will be necessary if the damage was the result of an internal event. The need for independent NRC assessment I
should be considered. The licensee will need to determine corrective actions to repair, test, inspect, and/or analyze affected systems and equipment.
These actions are required to restore or verify that the equipment will perform to design requirements.
Equipment modifications may also be required to ansure performance to design requirements.
Potential offsite emergency response impact for external events such as natural disasters, explosions, or riots should be considered. NRR should obtain information from FEMA headquarters reaffirming the adequacy of State and local offsite emergency plans and preparedness if an event raises reasonable doubts about amargency response capability.
a.
Licensee assesses damage to systems and NA I
components.-
I 5
Revised 7/16/97
\\.
t l NEED l STATUS ! RESP b.
NRC evaluates licensee damage assessment.
NA c.
Licensee determines corrective actions.
NA d.
NRC evaluates corrective actions.
NA B.4.3 Determina Rantart lamuas and Resolution X
RAP 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 section outlines steps to determine the restart issues and NRC's evaluation of their resolution.
a.
Review / evaluate licensee generated restart X
RAP issues.
b.
Independent NRC identification of restart X
C RAP issues c.
NRC/ licensee agreement on restart issues.
X l RAP d.
Evaluate licensee's restart issues X
RAP implementation process.
e.
Evaluate licensee's implementation verification X
sai process.
l 6
Revised 7/16/97
~. - -. -
.9 4
I lNEED STATUS RESP I c.
Conduct Commissioner assistants' briefing.
NA l
d.
Issue Commission paper (NRR).
NA Cognizant Federal agencies notified (i.e.,
NA e.
f.
State and local officials notified (Region).
NA p.
Congressional notification (NRR)
NA B.3 ESTABLISH AND ORGANIZE THE NRC REVIEW PROCESS C
RAP a.
Establish the Restart Panel.
X b.
Assess available information (i.e.
X RAP inspection results, licensee self assessments, industry reviews).
c.
Obtain !nput from involved parties both X
RAP within NRC and other Federal agencies such as FEMA, EPA, DOJ.
I d.
Conduct Director SPO briefing.
X l
C l RAP e.
Conduct NRR Executive Team briefing X
l f.
Develop the case specific checklist X
C RAP I
(CSC).
g.
Develop the Restart Assessment Plan.
X C
RAP h.
Director SPO approves Restart X
C DSPO Assessment Plan.
1.
NRR Director approves Restart X
C DNRR Assessment Plan.
J.
Implement Restart Assessment Plan.
X RAP k.
Modify order as necessary X
NRR l
B.4 l REVIEW IMPLEMENTATION l
l l
l 4
Revised 7/16/97
.-., ~.
?..
4
,4 l
!NEED l STATUS ! RL B.1 INITIAL NRC RESPONSE NA The facts, the causes, and their apparent impacts should be established early in the process. This information will assist the NRC in characterizing the problems, the safety significance, and the regulatory issues. Early management appraisal of the situation is also important to ensure the proper immediate actions are taken. The following items should have been completed or should be incorporated into the CSC as appropriate. Refer to Section 5.02 of this manual chapter for additional information.
a.
Initial notification and NRC management NA discussion of known facts and issues b.
Identify / implement additionalinspections (i.e.
NA AIT, llT, or Special) (Region).
c.
Determine need for formal regulatory response NA (l.a. order or CAL).
d.
Identify other parties involved (i.e., NRC NA Organizations, other Federal agencies, industry organizations).
B.2 NOTIFICATIONS NA 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 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. -
e.
Issue Daily and Directors Highlight (NRR).
NA b.
Issue preliminary notification (Region).
NA 3
Revised 7/16/97
4J~
l.
l NEED l STATUS RESP-Coordinates and implements those actions X
RAP e.
prescribed in the Restart Assessment Plan that have been determined to be the Office of Special Project's responsibility. These include, l
when appropriate, interactions with State and local agencies and with regional offices of Federal agencies.
i f.
In conjunction with NRR, reviews and X
RAP determines the acceptability of licensee's
'",'Ti corrective action program.
unn g.
Approves restart of the shutdown plant, X
DsPo following consultation with the EDO and the Director of NRR, and approval / vote by the Commission.
4.03 l Director SPO Acts as the focal point for discussions within X
DSPO a.-
NRR to establish the appropriate followup actions for a plant that has been shut down.
4.04 Deputy Director, Licensing a.
Coordinates participation in followup X
conference calls and management discussions i
to ensure that the Director SPO are directly involved, when appropriate, in followup action.
b.
Coordinates and implements actions prescribed X
DSPOL in the Restart Assessment Plan that have been determined to be Licensing's responsibility.
These include, where applicable, appropriate NRC Office or NRR Division interaction with other Federal agencies (e.g., Federal-Emergency Management Agency (FEMA),
Department of Justice (DOJ)) pursuant to any l
applicable Memoranda of Understanding.
2 Revised 7/16/97
ko 4
MILLSTONE RESTART ASSESSMENT PLAN ENCLOSURE (4)
MILLSTONE UNIT ALL UNITS RESTART APPROVAL (MCO350)
The following items are considered applicable to the restart of all Millstone Units:
RESPONSIBILITIES AND AUTHORITIES l
lNEED l STATUS l RESP 4.01 Director. Soecial Protects Office (SPO). Notifies the X
C NRR Executive Director for Operations (EDO) and the Commission, as appropriate, of the NRC actions taken concerning shutdown pl6nts and the proposed follnwup plan.
4.02 Director. Sometal Protects Office X
C DSPO a.
Discusses with the Deputy Executive Director for Nuclear Reactor Regulation, Regional Operations and Research, the Office of Enforcement (OE), and NRR, as appropriate, the need for an order or confirmatory action letter (CAL) specifying the actions required of the licensee to recolve NRC approval to restart the plant and the proposed followup plan.
b.
Decides, in consultation with the NRR X
C DSPO Associate Director for Projects, whether this manual chapter applies to a specific reactor
- restart, c.
In coordination with the NRR Associate X
C DSPO Director for Projects, decides whether to establish a Restart Panel.
d.
Develops a written Restart Assessment Plan, X
C RAP including a case-specific checklist, to assign responsibilities and schedules for restart actions and interactions with the licensee and outside organizations.
t Revised 7/16/97
.