ML20236G204
| ML20236G204 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/29/1998 |
| From: | Travers W NRC (Affiliation Not Assigned) |
| To: | Callan L NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| Shared Package | |
| ML20236G168 | List: |
| References | |
| NUDOCS 9807060158 | |
| Download: ML20236G204 (19) | |
Text
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UNITED STATES g.
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NUCLEAR REGULATORY COMMISSION t
WASHINGTON D.C. 20555-0001 g ***o o
June 29,1998 i
MEMORANDUM TO:
L. Joseph Callan Executive Director for Operations THRU:
d$i.-
irector Office of Nuclear Reactor Regulation s
FROM:
William D. Travers, Director
\\
Special Projects Office M\\ C
$UBJECT:
RESTART OF MILLSTONE NUCLEAR POWER STATION l
UNIT 3 In SECY 98-090, " Selected issues Related to Recovery of Millstone Nuclear Power Station Unit 3,* of April 24,1998, and SECY 98-119, " Remaining issues Related to Recovery of Millstone Nuclear Power Station Unit 3,* of May 28,1998, the staff described its final assessment of key issues related to the licensee's readiness to restart Unit 3. In SECY 98-119, the staff also provided its recommendation to the Commission that it provide its restart authorization for Unit 3. The Commission provided this authorization in its staff requirements memorandum (SRM) of June 15,1998. In the SRM the Commission designated the Executive Director for Operations (EDO) as the senior manager responsible for verifying the satisfactory completion of the appropriate aspects of inspection Manual Chapter (MC) 0350, " Staff j
Guidelines for Restart Approval," and approving commencement of actions to restart Unit 3.
The purpose of this memorandum is to inform you that the Millstone Restart Assessment Panel i
(Panel) has completed all of its activities associated with the execution of Inspection Manual Chapter (MC) 0350, " Staff Guidelines for Restart Approval," and has completed its review of all i
of the key technical and programmatic issues captured in the Unit 3 Restart Assessment Plan (RAP). A copy of the MC 0350 checklist is enclosed (Attachment 1) with the only open items l
being final restart approval by the EDO and post-restart approval notifications. The Panel has met on a number of occasions to assess restart-related issues that remained at the time of the June 2 Commission meeting or which have emerged since then. Based on the Panel's determination that these issues have been satisfactorily resolved, the Panel is recommending that you provide approval for Northeast Nuclear Energy Company (NNECO) to restart Millstone Unit 3 as requested by the licensee in its letter of June 29,1998 (Attachment 2).
Separately I have forwarded a letter which provides your approval for NNECO to commence restart activities and a memorandum to the Commission indicating that you have taken the action to approve commencement of restart activities. The staff is prepared to execute its l
augmented oversight of restart and power ascension operations, as delineated in the attached l
- restart and power ascension inspection plan (Attachment 3). As described in NNECO's May 1
20,1998, letter, and discussed in my response of June 16,1998, there are four intermediate hold points at which the NRC and NNECO will compare its assessments of plant and organizational performance and determine if any NRC concerns need to be dispositioned l
ATTACHMENT 1 9907060158 900629 PDR ADGCK 05000423 l.
P PDR E__ _ __
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2 before the licensee increases power to the next plateau. Additionally, after the licensee reaches 100 percent power, NNECO and the NRC will conduct a final assessment to determine if the licensee is ready to continue power operations, it is anticipated that the staff will conduct a public meeting with the licensee to discuss the overall results of its assessment of the restart and power ascension process.
The staff will continue to keep you and the Commission infonmed of any pertinent issues that I
emerge during the licensee's restart and power ascension program.
Attachments:
1.
MC 0350 Checklist 2.
NNECO Restart Readiness Letter of June 29,1998 3.
NRC Restart and Power Ascension inspection Plan l
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i ATTACHMENT 1
MILLSTONE RESTART ASSESSMENT PLAN MILLSTONE UNIT 3 RESTART APPROVAL (MC 0350)
RESPONSIBILITIES AND AUTHORITIES l
lNEED l STATUS l RESP 4.01 Director. Soecial Projects Office (SPO). Notifies the X
C NRR Executive Director for Operations (EDO) and the Commission, as appropriate, of the NRC actions taken concerning shutdown plants and the proposed followup plan.
4.02 Director Soecial Projects 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 receive NRC approval to restart the plant and the proposed followup plan.
b.
Decides, in consultation with the NRR Associate X
C DSPO Director for Projects, whether this manual chapter applies to a specific reactor restart.
c.
In coordination with the NRR Associate Director for X
C DSPO 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.
e.
Coordinates and implements those actions prescribed X
C RAP in the Restart Assessment Plan that have been determined to be the Office of Special Project's responsibility. These include, when appropriate, interactions with State and local agencies and with regional offices of Federal agencies.
Revised June 29,1998
.. l.. ~
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7 NEED STATUS RESP f.
In conjunction with NRR, reviews and determines the X
C RAP acceptability oflicensee's action program.
$'i T
NRR g.
Approves restart of the shutdown plant, following NA consultation with the EDO and the Director of NRR, and approval / vote by the Commission.
'4.03
- Director SPO a.
- Acts as the focal point for discussions within NRR to X
C DSPO
. establish the appropriate followup actions for a plant that has been shut down.
4.04 Deputy Director, Licensing Sm a.
. Coordinates participation in followup conference calls X
C and management discussions to ensure that the Director SPO is directly involved, when appropriate, in followup action.
4 b.
Coordinates and implements actions prescribed in the X
C DSPOL 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 Just:ce (DOJ)) pursuant to any applicable Memoranda of Understanding.
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 1he NRC in characterizing the problems, the safety 4 significance, and the regulatory issues.' Early management f
i l
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.'
- Revised June 29,1998 '
i 8
NEED STATUS RESP a.
- Initial notification and NRC management discussion of NA known facts and issues b.
Idr.ntify/ implement additionalinspections (i.e. AIT, llT, NA or Special)(Region).
I c.
Determine need for formal regulatory response (i.e.
NA order or CAL).
l d.
Identify other parties involved (i.e., NRC NA l.
Organizations, other Federal agencies, industry i
organizations).
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l Revised June 29,1998 l
1
V, l
l STATUS l RESP NEED B.2 NOTIFICATIONS NA initial notification of the svent 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.
a.
Issue Daily and Directors Highlight (NRR).
NA b.
Issue preliminary notification (Region).
NA c.
Conduct Commissioner assistants' briefing.
NA d.
Issue Commission paper (NRR).
NA e.
Cognizant Federal agencies notified (i.e., FEMA, EPA, NA DOJ).
f.
State and local officials notified (Region).
NA g.
Congressional notification (NRR)
NA B.3 ESTABLISH AND ORGANIZE THE NRC REVIEW PROCESS a.
Establish the Restart Panel.
C RAP 4
X b.~
Assess available information (i.e. inspection X
-C RAP results, licensee self-assessments, industry
[ ting reviews).
Minutes I
L c.
Obtain input from involved parties both within X
C RAP NRC and other Federal agencies such as DSPOL L
l.
d.
Conduct Director SPO briefing.
X C
RAP e.
Conduct NRR Executive Team briefing (NRR).
X C
RAP f.
Develop the case-specific checklist (CSC).
X C
RAP g.
Develop the Restart Assessment Plan.
X C
RAP h.
Director SPO approves Restart Assessment X
C DSPO Plan.
Revised June 29,1998
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2 NEED STATUS RESP l.
NRR Director approves Restart Assessment X
C DNRR
' Plan.
j.
Implement Restart Assessment Plan.
X C
RAP k.
Modify orders as necessary X
NA NRR B.4 l REVIEWIMPLEMENTATION l
l-B.4.1 Root Causes and Corrective Areians OSTI C
W a.
Evaluate findings of the special team X
inspection.
b.
Licensee performs root cause analysis and X
C NU develops corrective action plan for root causes.
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c.
NRC evaluates licensee's root cause X
C RAP determination and corrective action plan.
[h B.4.2 B.4.2 - Assessment of Eaulnment Damana NA i
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 intemal event. The need for independent NRC assessment should be considered. The licensee will need to determine corrective adions 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 ensure performance to design requirements.
Potential offsite emergency response impact for extemal 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 emergency response capability.
L Revised June 29,1998 l
1
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?
f NEED STATUS RESP
[
a.
Licensee assesses damage to systems and NA components.
l' b.
- NRC evaluates licensee damage assessment.
NA c.
Licensee determines corrective actions.
NA l
f d.
NRC evaluates corrective actions.
NA 1
l l
l B.4.3 Determine Restart lasues and ResoMian X
C RAP l ~-
l The establishment of the restart issues that require resolution before restart demands a clear understanding of the issues l
and the actions required to address those issues by both the NRC and the licensee. This section outlines steps to I
determine the restart issues and NRC's evaleetion of their resolution.
a.
Review / evaluate licensee generated restart issues.
X C
- b. '
independent NRC identification of restart issues
-X C
RAP c.
NRC/ licensee agreement on restart issues.
X C
RAP d.
Evaluate licensee's restart issues implementation X
C RAP l
process.
e.
Evaluate licensee's implementation verification X.
C SRI-SIL process; OSTI dM I
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Revised June 29,1998 l
i
l RESP NEED STATUS-B.4.4 Obtain Comments Since some shutdowns involve a broad number of issues, solicitation of comments from diverse sources may be appropnate. 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 concoming the adequacy of state and local emergency planning and preparedness must be obtained from FEMA headquarters through NRR.
a.
Obtain public comments.
RAP X
C b.
Obtain comments from State and Local X
C Regional Officials (Region).
SLO 4W' c.
Obtain comments from applicable Federal X
C RAP agencies.
B.4.5 Clomeout Actions When the actions to resolve the restart issues and significant concems are substantially complete, closeout actions are needed to verify that planned inspections and verifications are complete.. The licensee should certify that corrective actions
' l required before restart are complete and that the plant is physically ready for restart. This section provides actions associated with completion of significant NRC reviews and preparations for restart.
RAP X
C OST a.
Evaluate licensee's restart readiness self-assessment.
l f
b.
NRC evaluation of applicable items from Section C X
C RAP "lSSUES" complete.
l c.
Restart issues closed.
X C
RAP l
SRI OSTI l
d.
Conduct NRC restart readiness team inspection.
X C
oSTi
. e.
issue augmented restart coverage inspection plan.
X C
OSTI I
RAP t
Revised June 29,1998
_____.___._.__m_
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lNEED l STATUS lRESP f.
Comments from other parties considered.
X C
RAP g.
Determine that all conditions of the Order / CAL are X
C RAP satisfied.
ICAVP i
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h.'
Re-review of Generic Restart Checklist complete.
X C
RAP j
SRI-NU I
B.5.
RESTART AUTHORIZATION (B.5)
L When the restart review process has reached the point that L
the issues have been identified, corrected, and reviewed, a l
restart authorization process is begun. At this point the i
Restart Panel should think broadly and ask: "Are all actions substantially complete? Have we overlooked any items?"
a.
Prepare restart recommendation document and basis X
C RAP for restart.
b.
NRC Restart Panel recommends restart X
C RAP c.
No restart objections from other applicable HQ offices.
X C
DSPOL
- d. -
No restart objections from applicable Federal X
C RAP l
agencies.
l e.
DSPO concurs in restart recommendation X
C DSPO
(
f.
NRR Director concurs in restart recommendation.
X C
NRR l
g.
EDO concurs in restart recommendation when
'NA required.
h.
Conduct ACRS briefing when requested (NRR).
X NA SPO u
1.
Conduct Commission briefing when requested.
X C
DSPO J.
Commission approves restart.
X C
coMM k.
EDO authorizes restart.
X EDO
- 1 i
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lNEED l STATUS lRESP B.6 RESTART AUTHORIZATION NOTIFICATION (B 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, a.
Commission (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 written X
NA SPO notification if the ACRS requests a briefing) (NRR).
e.
Applicable Federal agencies.
X C
RAP f.
Public Affairs.
X OPA g.
State and local officials.
X GLO h.
Citizens or groups that expressed interest during the X
RAP restart approval process.
l.
Issue staff concems memorandum.
X C
RAP C.1.1 Root Cause Assessment a.
Conditions requiring the shutdown are clearly X
C RAP understood.
ACR 7007 b.
Root causes of the conditions requiring the shutdown X
C RAP are clearly understood.
c.
Root causes of other significant problems are clearly X
C RAP understood.
Revised June 29,1998
f.._.
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NEED STATUS RESP d.
Effectiveness of the root cause analysis program.
X C
40500 s
RAP.
OSTI i
C.1.2 Damaae Assessment a.
Damage assessment was thorough and NA l
comprehensive.
l b.
Corrective actions clearly restored systems and NA equipment or verified they can perform as designed.
.C.1.3 Corrective Actions l.
a.
Thoroughness of the corrective action plan X
C RAP 40500 l.
b.
Completeness of corrective action programs for X
C SRI specific root causes.
40500 L
c.
Control of corrective action item tracking.
X C
SRI 40500-d.
Effective corrective actions for the conditions requiring X
C SRI the shutdown have been implemented.
[$
e.
Effective corrective actions for other.significant X
C SRI problems have been implemented.
OS CA j
40500 l'
f.
Control of long-term corrective actions.
X C
SRI (Backlog Management Plan)
[$
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g.
Effectiveness of the corrective action verification X
C
' SRI process.
40500 i
Revised June 29,1998 i
lNEED' STATUS RESP C.1.4 Self-Assessment Onnahility
)-
The occurrence of an event may be indicative of potential L
weaknesses in the licensee's self-assessment capability. A l
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 effectiveness in ensuring effective self-assessment is treated separately, s.
Effectiveness of Quality Assurance Program.
X C
RAP 3
i 40500 b.
Effectiveness of Industry Experience Review Program.
X C
osTI-40500 l
c.
Effectiveness of licensee's Independent Review X
C SRI Groups.
fg
]
s d.
. Effectiveness of deficiency reporting system.
X C
SRI j
oSTI I
40500 e.
Staff willingness to raise concems.
X C
SPo(L)
RAP f.
Effectiveness of PRA usage.
X C-40500 osTi g.
Effectiveness of commitment tracking program.
X C
Review applicable external audits X
C 40500 l
osTI I
1.
Quality of 10 CFR 50.72 and 50.73 reports.
X C
SRI C.2.1 Management Oversight and Effectiveness l
a.
Goals / expectations communicated to the staff.
X C
osTI L
40500 l
b.
Demonstrated expectation of adherence to X
C SRI procedures.
[$
q c.
Management involvement in self-assessment X
C RAP 40500 and independent self-assessment capability Revised June 29,1998 i
.____-_________-_-_a
l NEED STATUS RESP 1
l d.
Effectiveness of management review committees.
X C
SRI OSTI 40500 e.
Management's demonstrated awareness of day-to-day X
C SRI operational concems.
OSTI f.
Management's ability to identify and prioritize X
C SRI significant issues.
oS
,g g.
Management's ability to coordinate resolution of X
C SRI significant issues.
08T
,05 h.
Management's ability to implement effective corrective X
C SRI actions.
OSTI 40500 C.2.2 Manaoement Sucoort a.
Impact of any management reorganization.
X C
RAP 40500 b.
Effective and timely resolution of employee concerns.
X C
RAP SPO(L)
SCWE Adequate engineering support as demonstrated by X
C DRS c.
timely resolution ofissues.
fCA d.
Adequate plant administrative procedures.
X C
SRI 40500 OSTl e.
Effective information exchange with other utilities.
X C
SRI 40500 OSTI f.
Participation in industry groups.
NA g.
Effectiveness of Emergency Response Organization.
X C
DRS h.
Coordination with offsite eme gency X
C DRS planning officials.
C.3.1 Assessment of Staff RAP a.
Demonstrated commitnient to achieving X
C SRI improved performance.
b.
Demonstrated safety consciousness.
X C
OST SRI SPO(L)
SWCE Revised June 29,1998
1 NEED STATUS RESP c.
Understanding of management's expectations and X
C OST goals.
40500 d.
Understanding of plant issues and corrective actions.
X C
OST: -
SRI 40500 e.
Qualifications and training of the staff.
X C
OST:
f.
Staffs fitness for duty.
NA g.
Attentiveness to duty.
X C
OST h.
Level of attention to detail.
X C
OSTI 1.
Off-hour plant staffing.
X C
SRI J.
Staff overtime usage.
X C
SRI 40500 k.
Procedure usage / adherence.
X C
SRI 40500 oSTI 1.
Awareness of plant security.
X C
DRS m.
Understanding of offsite emergency planning issues.
X C
DRS C.3.2 Assessment of Coroorate Sucoort and Site Enaineerina Sucoort X
C OST:
a.
Corporate staff understanding of plant issues.
b.
Corporate staff site specific knowledge.
X C
OST:
c.
Effectiveness of the corporate / plant interface X
C OST:
meetings.
d.
Corporate involvement with plant activities.
X C
OSTI e.
Effectiveness of site engineering support.
X C
Effectiveness of the site design modification process.
X C
ICAVP OST:
g.
Effectiveness of licensing support.
X C
RAP h.
Coordination with offsite emergency planning officials.
X C
DRS l
Revised June 29,1998
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NEED STATUS RESP..
C.3.3 Operatorlasues a.
Licensed operator staffing meets requirements and licensee goals.
X C-DRS IR 98-206 b.
Level of formality in the control room.
X C
osTi SRI 1R 98-206 L
c.
Effectiveness of control room simulator training.
X C
DRS IR 98 206 d.
Control room / plant operator awareness of equipment X
C osTi status.
SRI e.
Adequacy of plant operating procedures.
X C
Procedure usage / adherence.
X C
SRI osTi g.
Log keeping practices.
X
.C osTI
~
C.4 ASSESSMENT OF PHYSICAL READINESS OF THE PLANT a.
Operability of technical specification systems.
X C
osTI MODE 2 b.
Operability of required secondary and support X
C osTi 4
systems.
c.
Results of pre-startup testing.
X C
SPo osTI d,
' Adequacy of system lineups.
X C
osTI e.
Adequacy of surveillance tests / test program.
X C
osT f.
Significant hardware issues resolved (i.e. damaged X
C osTi equipment, equipment ageing, modifications).
g.
Adequacy of the power ascension testing program.
X C
osTI SRI h.
. Effectiveness of the plant maintenance program.
X C
osTi DRS 1.
Maintenance backlog managed and impact X
C osTI i
on operation assessed.
Revised June 2g,1998 j
l
l NEED STATUS RESP i
J.
Adequacy of plant housekeeping and equipment X
C OSTI storage.
C.5 ASAFAMENT OF COMPLIANCE WITH REGULATORY REQUIREMENTS a.
' Applicable license amendments have been issued.
X C
RAP b.
Applicable exemptions have been granted.
X NA RAP.
c.
. Applicable reliefs have been granted.
X C
RAP d.
Imposed Orders have been modified or rescinded.
X C
RAP e.
Significant enforcement issues have been resolved.
X C
Allegations have been appropriately addressed.
X C
10 CFR 2.206 Petitions have been appropriately X
C NRR addressed.
h.
Atomic Safety and Licensing. Board hearings have NA No ASLB been completed.
f*i'4 required before restart C.6 COORDINATION WITH INTERESTED AGENCIES AND PARTIES a.
Federal Emergency Management Agency X
C DRS.
DSPO (L) b.
Environmental Protection Agency NA l
c.
Department of Justice X
C OE 01 DSPO f
d.
Department of Labor X
C OE e.-
Appropriate State and local officials X
C SLO f.
Appropriate publicinterest groups X
C RAP g.
Local news media X
C OPA Revised June 29,1998 -
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ATTACHMENT 2 1
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. JUN-29-98 MON 10:54 AM NUCLEAR LICENSlHG SVCS.
FAX HO. 860 440 2091 P,02 i Northeast L NuclearEnergy Rope Faiy WRom 166). W Mwd.cT 06385 wn N.ci,P rsi..i Northeast Nuclear Enwgy Cesapany P.o.s 12a
- w. u.,a. cT n o ss.o:2s (860) 447 1791 Fax (860) 444 4277 The Norskast Udh Sy.iem JUN 2 91998 Docket No. 50-423 B1730_7_
U.S. Nuclear Regulatory Commission l
Attention: Document Control Desk Washington, D.C. 20555 Millstone Nuclear Power Station, Unit No. 3 Readiness For Ascension To Mode 2 Northeast Nuclear Energy Company (NNECO) committed, in a May 20,1998 letter, to notify the NRC Staff when ready for ascension to Mode 2 at Millstone Unit No. 3.
In preparation for this evolution, the Unit 3 Management Team has assessed the elements required to be completed and determined that the Mitistone Unit No. 3 is ready for ascension to Mode 2.
Nuclear Oversight has performed their own independent assessments and concurs with this conclusion.
If there are any further questions on the information provided in this letter, please contact Mr. D. A. Srnith at (860) 437-5840.
i Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY
)D l
1p Brdce D. Kenyo President & Chief-xecutive Officer
[
See Page 2 cc:
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JUS-29-98110N 10:55 AM NUCLEAR LICENSING SVCS.
FAX NO. 860 440 2091 P,03 g 73 7 hear Regulatory Cornmission U
L. J. Callan, Executive Director of Operations ec:
H. J. Miller, Region 1 Administrator l
J. W. Andersen, NRC Project Manager, Millstone Unit No. 3 A. C. Cerne. Senior Resident inspector, Millstone Unh No. 3 1
i W. D. Travers, PhD, Director, Special Projects Office W. D. Lanning, Deputy Director of Inspection - Special Projects Office J. P. Durr, Branch Chief, inspections, Special R(ojects Office l
I 4
4 i
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'JUN-29'-98 MON 10:55 AM NUCLEAR 1.10ENSING SVCS.
FAX N0. 860 440 2001 P.04 L
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Docket No. 50-423 B17307 i
P Millstone Nuclear Power Station, Unit No. 3 NNECO's Commitments 4
.. /
[
June 1998 j
j.
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c._ _.
. JUN49-98 MON 10:55AM NUCLEAR LICENSING SVCS, FAX N0.;860 440 2091 P.05 U.S. Nuclear Regulatory Commission
. s.
B17307tAttachment itPage 1 Enclosure List of Regulatory Commitments The following table identifies those actions committed to by NNECO in this document.
Please notify the Manager - Millstone Unit No. 3 Regulatory Compliance at the Millstone Nuclear Power Station Unit No 3 of any questions regardin thi d g
s ocument or any associated regulatory commitments.
Commitment Committed Date or Outage None N/A 4
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e ATTACHMENT 3 L
l l
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June 25,1998 l
MILLSTONE UNIT 3 REACTOR STARTUP INSPECTION PLAN 1.
BACKGROUND L
l At the time of restart of Millstone Unit 3, the Unit will have been shutdown in excess of two years. Based on an existing Commission Order, Commission authorization will have been obtained prior to Unit 3 restart. Because of this long shutdown period, the NRC will provide additional inspection coverage during initial restart of the unit to gain confidence in the licensee's ability to safely operate the plant after such a lengthy shutdown. NRC Inspection Procedure 93802, I
" Operational Safety Team inspection (OSTI)", will have been completed during licensee initial operations in Modes 4 and 3. For this reason, inspection objectives normally performed by the OSTI while a plant is at power will not need to be repeated during critical operations inspection coverage.
l This inspection plan is to augment the normal resident inspection core inspection 1 -~
program during normal plant operations. The augmented inspection activity will be used to take credit for the NRC inspection program in the following areas:
I IP 62707 Maintenance Observation (Core)
=
IP 61726 Surveillance Observations (Core)
IP 71707 Plant Operations (Core)
)
i IP 71715 Sustained Control and Plant Observation (Regional Initiative)
IP 71750 Plant Support Activities (Core) l In addition to the guidance provided by this picn, guidance provided in the above l
inspection procedures shall be used, as applicable.
II.
INSPECTION OBJECTIVES i~
a.
Monitor licensee's conformance to their procedure SPROC-97-3-30, " Plant Startup and Power Ascension Sequencing Procedure" and OP 3274, "Startup and Power Ascension Plan for startup and Mid-Cycle 6 Outage."
b.
Verify that the plant is being operated safely and in conformance with l
regulatory requirements.
l c.
. Assess licensee management decision making process.
4 I
L -___--
r-~--
t l
lll.
INSPECTION STAFFING DURING REACTOR STARTUP AND CRITICAL OPERATIONS
- MODE 2 THROUGH MODE 1 l
't Start augmented inspection within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of approach to Mode 2 a.
b.
Secure augmented coverage during any st tdown of 5 days or longer and at completion of 30% power plateau c.
Inspection staffing (1)
One manager (branch chief or above) onsite Provides overall direction a:
Coordinates with licensee and NRC management Inspects licensee management activities (2)
Senior Resident inspector Perform normal SRI duties i
Provide coordination with NRC onsite manager and inspectors.
periorming augmented inspection coverage (3)
Two inspectors for augmented inspection coverage Control Room observations Roving coverage for general plant observations IV.
INSPECTION ACTIVITIES WHILE ON SHIFT -
a.
Ooerations (1)
Monitor licensee's performance of SPROC-97-3 30 and OP 3274 (2).
Observe the conduct of operations personnel both inside and outside the control room.
j 1
Changes in plant operating conditions, tests, and surveillance.
Quality of operator professionalism, attentiveness, awareness of plant status and communications.
i Operator performance issues as previously identified in inspection Report 97-83, " Operational Safety Team inspection" l
Conduct of plant evolutions.
1 4
' =
Response to alarms and other abnormal indications Overall planning and control of plant and shift activities.
a
' (
Following of plant procedures during the conduct of changes to
=
plant operations.
(3)
' Assess the effectiveness of shift turnovers.
I
-(4)
Evaluate access control and traffic in the control room. Determine
. whether collateral duties of the operators have an adverse effect on.
their ability to operate the plant safely.
e
' l (5)
Assess the adequacy of annunciator response, number of l
continuously lit annunciators, and response to out of service equipment and components.
.(6)'
Determine the effectiveness with which operations appropriately controls support activities in progress, including maintenance, trouble shooting, and testing activities which can potentially influence plant operations.
(7).
Periodically observe auxiliary operators during routine rounds, or otherwise tour the plant. Assess the adequacy of housekeeping.
(8)
Verify compliance with Technical Specification and license.
(9)'
Evaluate the status of control room annunciators, alarms, and recorders. Verify the acceptability of the licensee's methodology for compensatory measures for those indications not operatir.g properly.
'(10)
Assess licensee performance for power ascension hold points in SPROC 97-3 30 approximately at the 30 percent,50 percent, 75 percent and 90 percent power levels.
b.
Surveillance Testing
^
l Observe e number of surveillance tests being performed by licensee personnel in the mechanical, electrical, and instrumentation and control
' maintenance groups and verify that:
(1):
Test results meet technical specification acceptance criteria.
(2)
Surveillance testing is completed within the required technical specification frequency.-
4 +
17 c.
Maintenance Activities Review licensee performance in conducting corrective and preventive maintenance activities in progress in accordance with NRC IP 62707.
d.
Mannaement Review
.(1)
Evaluate licensee management.'s attention to transitional controls.
Management's oversight and controls in daily work and preparation activities.
'(2)
Assess management involvement in the restart effort.
Management effectiveness in directing restart activities for around-the-clock activities.
Management assurance that technical and other support staff coverage is available at all times.
Where significant management turnover has occurred, verify that adequate training was completed.
Review management involvement and performance as related to SPROC-97-3 30 and OP 3274.
Review management input to power hold point evaluations.
- Assure that licensee management decisions are made in a-conservative manner
. V.
DOCUMENTATION a.
- Inspection activities will be documented in the current resident inspection report.
b.~
' Inspection activities should be charged to the following core inspection program procedures (as applicable):
(1)-
Maintenance Observation
- i (2)
IP 61726-Surveillance Observations -
(3)
IP 71707 Plant Operations i
(4)-
IP il715 Sustained Control Room and Plant Observation i
'(5)
IP 71750 Plant Support Activities
.w
'Cila__i_ _. _ _ _ _ _ _ _. _ _. _ _ _ - - -
I.,
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. UNITED STATES g'g
[
NUCLEAR REGULATORY COMMISSION e
WASHINGTON, D.C. 30seHo01 4,,,*;
Ju'ne 29, 1998 l
1 Mr. Bruce Kenyon President and Chief Executive Officer Northeast Nuclear Energy Company.
t P.O. Box 128 '
l Waterford, CT 06385 D' ear Mr. Kenyon:
On June 15,1998, th'e Commission concurred in the NRC staff's assessment that Northeast Nuclear Energy Company (NNECO) had taken appropriate corrective actions to support the restart of Millstone Unit 3 and provided its restart authorization, subject to satisfactory
. completion of all remaining issues requiring NRC verification. As I noted in my letter of
= June 16,1998, the Commission's restart authorization resulted in Unit 3 being categorized as a
. watch list Category 2 plant instead of a Chtegory 3 plant. As part of its. restart authorization, I was designated by.the Commission as the NRC's senior manager responsible for verifying that
- appropriate aspects of Inspection Manual Chapter (MC) 0350, " Staff Guidelines for Restart Approval," are completed and for approving commencement of actions to restart Unit 3. ' In your.
June 29,1998, letter, you stated that Millstone Unit 3 was ready for restart. After careful review of the results of your restart-related activities and the staff's assessment of these results, I have concluded that Millstone Unit 3 is ready for restart. A summary of the NRC's review
- activities follows.
Millstone Unit 3 was shutdown on March 30,1996, after it was determined that containment.
isolation valves for the auxiliary feedwater turbine-driven pump were inoperable because the valves did not meet NRC requirements. On August 14,1996, the NRC issued a Confirmatory Order (Order) directing NNECO to contract with a third-party to implement an Independent Corrective Action Verification Program (ICAVP) to verify the adequacy of your efforts to
- . establish adequate design bases and design controls.- On October 24,1996, the NRC issued an Order directing that before restarting any Millstone unit, NNECO develop and submit to the
' NRC a comprehensive' plan for reviewing and dispositioning safety issues raised by your a
- employees and for ensuring that employees who raise safety concerns can do so without fear of retaliation. This Order directed NNECO to retain an independent third-party to oversee implementation of your comprehensive plan.
In November 1996, the NRC created a new organization, the Special Projects Office (SPO) within the Office _ of Nuclear Reactor Regulation, to provide a specific management focus on licensing and inspection activities required to support an NRC decision on restart of the Millstone units.~ The staff's inspection and assessment efforts were conducted in 'accordance with MC 0350, including the development of a specific Restart Assessment Plan (RAP) for each Millstone unit. - The RAP was revised several times to capture emerging issues and was the major tool used by the Millstone Restart Assessment Panel (Panet) to track Millstone recovery
- efforts.
~-
ATTACHMENT 2 jh~lON$Y W'
u a
1 f
' B.D. Kenyon 2
June 29, 1998 L
The NRC has performed many inspections since March 1996, to evaluate NNECO's progress in resolving performance issues.. These activities included oversight and inspections of the ICAVP l
and employee concems program (ECP), augmented resident inspector staff inspections, L
specialist reviews of discrete areas by SPO, regional, and headquarters staff, and multi-disciplined team inspections.. These effetts included inspection of 86 technical and programmatic restart issues contained in revision 4 of the NRC's RAP. Public meetings were conducted approximately every 6-8 weeks to solicit public input on the Millstone recovery -
l-activities, and many publicly observable meetings on both technical and programmatic issues were conducted at the site.; An operational safety team inspection was conducted during April 1998, and a public exit was held on May 5,1998.- Seven Commission meetings were L
conducted to provide the status of recovery efforts at Millstone, including the two most recent
. meetings held on May 1 and June 2,1998, during which the restart readiness of Unit 3 was L
'specifically addressed.
These N' RC activities, inspections, and licensing reviews led to additional issues that had to be 1
addressed before Unit 3 could restart. The staff provided the Commission with its final assessment of key Unit 3 RAP issues in SECY 98-090, " Selected lasues Related to Recovery
. of Millstone Nuclear Power Station, Unit 3," dated April 24,1998, and in SECY 98-119,
" Remaining issues Related to Recovery of Millstone Nuclear Power Station, Unit 3," dated i-May 28,1998, in SECY 98-119, the staff concluded that Northeast Nuclear Energy Company
.' (NNECO) had taken appropriate corrective actions to support restart of Millstone Unit 3. Over L
- the past month, the Panel has met frequently to review NNECO's efforts to resolve the remaining restart-related issues at Unit 3 and they have concluded that the issues have been adequately addressed to support the safe restart of Millstone Unit 3.
As noted in the Director of SPO's letter dated June 16,1998, the NRC will formally monitor your restart and power ascension program. This letter was written in response to Mr. Martin
' Bowling's letter of May 20,1998, in which he detailed NNECO's restart and power ascension program and provided several commitments, including the identification of four specific hold
' points during the ascension to full power. The commitments indicate that NNECO will assess
.i plant and organizational performance at each of these hold points, review the results of each of i
'- these assessments with the NRC, and disposition any NRC concems before increasing power.
These assessments should be coordinated with the NRC resident inspectors.
i In summary, the NRC agrees that Millstone Unit 3 is ready for restart. I am hereby providing my authorization for NNECO to commence activities to restart Unit 3.- If you have any questions regarding this matter, do not hesitate to call me.
c r
l Sincerely,
.c p
allan Ex ive Director for Operations Docket No. 50-423 cc: See'next page L
f, . ;.,
Millstone Nuclerr Power Station Unit 3 i
cc-L Lillian M. Cuoco, Esquire Joseph R. Egan, Esquire l
Senior Nuclear Counsel.
Egan & Associates, P.C.
L
. Northeast Utilities Service Company 2300 N Street, NW.
L P. O. Box 270 Washington, DC 20037 H rtford, CT 06141-0270 Mr. F. C. Rothen Mr. Kevin T. A. McCarthy, Director Vice President-Work Services Monitoring and Radiation Division Northeast Utilities Service Company Department of Environmental Protection P. O. Box 128 79 Elm Street Waterford, CT 06385 i
Hatford, CT 06106-5127 Emest C. Hadley, Esquire Regional Administrator, Region I.
1040 B Main Street U.S. Nuclear Regulatory Commission P.O. Box 549 475 Allendale Road West Wareham, MA 02576 King of Prussia, PA 19406 1
Mr. John Buckingham E
First Sebctmen.
Department of Public Utility Control :
1 Town of Waterford Electric Unit H;h of Records -
10 Liberty Square
. 200 Boston Post Road -
New Britain, CT 06051
.Waterford, CT 06385 Mr. James S. _ Robinson, Manager Mr. Wayne D. Lanning Nuclear Investments and Administration Deputy Director ofInspections..
New England Power Company Special Projects Office 25 Research Drive 475 Allendale Road -
Westborough, MA. 01582 -
- King of Prussia, PA 19406-1415-l Mr. John Streeter -
Mr. M. H. Brothers Recovery Officer - Nuclear Oversight Vice President-Millstone Unit 3 Northeast Utilities Service Company-N:rtheast Nuclear Energy Company P. O. Box 128 l
~ P.O. Box 128 Waterford, CT 06385 l
Waterford, CT 06385
-l Deborah Katz, President i
_ Mr. M. R. Scully, Executive Director Citizens Awareness Network l
- C:nnecticut Municipal Electric -
P.O. Box 83
. Energy Cooperative' Shelbume Falls, MA 03170 30 Stott Avenue Norwich, CT 06360 Mr. Allan Johanson, Assistant Director Office of Policy and Management -
Mr. David Amerine -
Policy Development and Planning l
LVice President-Human Services Division
_ Northeast Utilities' Service Company 450 Capitol Avenue - MS# 52ERN P. O. Box 128 L P. O. Box 341441.
Waterford, CT 06385 Hartford, CT 06134-1441 L
j, 'e l
Millstone Nuclear Power' Station.
Unit 3' l
CC*.
The Honorable Terry Concannon Mr. William D. Meinert Nuclear Energy Advisory Council Nuclear Engineer Room 4035 Massachusetts Municipal Wholesale 1
-: Legislative Office Building.'
Electric Company Capitol Avenue P.O. Box 426 Hartford,CT 06106 Ludlow, MA 01056
' Mr. Evan W. Woollacott -
Attomey Nicholas J. Scobbo, Jr.
Co-Chair Ferriter, Scobbo, Caruso, Rodophele, PC -
Nuclear Energy Advisory Council 1 Beacon Street,11th Floor -
4128 Terry's Plain Road Boston, MA 02108 L.Simsbury, CT 06070.
Citizens Regulatory Commission -
Mr. John W. Beck, President ATTN: Ms. Susan Perry Luxton Little Harbor Corisultants, Inc.-
180 Great Neck Road
- Millstone'-ITPOP Project Office
. Waterford, CT 06385
. P.O. Box 0630 Niantic, CT 06357-0630
- Mr. B. D. Kenyon (Acting).
' Chief Nuclear Officer-Millstone.
Northeast Nuclear Energy Company-P.0; Box 128 Waterford, CT 06385 Mr. Daniel L Curry.
. Project Director,
- Parsons Power Group inc.
2675 Morgantown Road
' Reading, PA 19607
'Mr. Don Schopfer
. Verification Team Manager
~
Sargent & Lundy =
55 E. Monroe Street.
- Chicago, IL 60603
~<
g..
Mr. G. D. Hicks
~"
Director.- Unit 3
. Northeast Nuclear Energy Company; l
P.O. Box.128 Waterford, CT 06385.
' Senior Resident inspector Millstone Nuclear Power Station L
clo U.S. Nuclear Regulatory Commission P.. O. Box 513 Niantic, CT 06357
.t.
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