ML20138G997
| ML20138G997 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/14/1995 |
| From: | Eliason L Public Service Enterprise Group |
| To: | Martin T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20138G636 | List:
|
| References | |
| FOIA-96-351 LR-N95090, NUDOCS 9701030097 | |
| Download: ML20138G997 (111) | |
Text
E
?
Pubhc Service Electnc and Gas Company Leon R. Elleson Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 06038 609-339-1100 Chief Nuclear officer & President Nuclear Business Unit JUN 141995 LR-N95090 U.
S.
Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Attn: Mr. T. T.
Martin, Regional Administrator - Region I
Dear Mr. Martin:
RESPONSE TO CONFIRMATORY ACTION LETTER DATED JUNE 9, 1995 SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS: 50-272 AND 50-311 As we discussed in our telephone conversation on Thursday morning, June 8, 1995 and confirmed by your letter of June 9, 1995, this letter documents Public Service Electric & Gas Company's commitment to maintain Salem Unit Nos. 1 and 2 in a shutdown condition until we have conducted a structured review of long-standing equipment reliability and operability issues, including corrective maintenance and operator workarounds.
This review will also assess the effectiveness and quality of the management oversight and review of these matters.
Based on discussions with NRC Region I management, we understand the shutdown condition to be Mode 3, 4,
5 or 6.
This letter also confirms our commitment to perform a Significant Event Response Team review of the circumstances leading to and causing the Salem Unit 2 reactor trip, and to communicate our findings to you.
We are currently defining the actions we will perform during this forced outage.
Following completion of this scoping effort, we will meet with you to discuss these plans and to describe the restart readiness review process we will utilize to determine the operational readiness of both units.
The results of the restart process, once implemented, will be discussed with you in a subsequent meeting prior to placing either unit into service.
Sincerely, Y
I 1L f,
9701030097 961226 j
O'NEILL96-351 PDR
l I
i l
l Document Control Desk 2
JUN 14 E85 LR-N95090 C
.U.S.
Nuclear Regulatory Commission Document Control Desk i
Washington,.DC 20555 Mr.
L. N. Olshan, Licensing Project Manager - Salem U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. C.
S.
Marschall (SO9)
USNRC Senior Resident Inspector Salem Generating Station Mr. K. Tosch, Manager IV j
NJ Department of Environmental Protection Division of Environmental Protection Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 1
i t
l l
l l
l i
i 95 4933
. -. -.. - - -. - - ~ _. -
SENT BY:
6-S-35 : 4:51PM :
PSE&G Lic & REG ~
6103375354:s 3/ 4 i
CHARTER:
ESTABLISH NECESSARY ACTIONS FOR SALEM RESTART Consistent with the more aggressive management actions and higher standards encompassed in our IMPACT Plan, we have determined that prior to resuming plant operations at either of the Salem Units, we will assess and improve equipment reliability and continue to address management and process issues by completing our existing l
IMPACT Near-Term action plans. Any actions required for restart will be included in the IMPACT Plan to assure event. free management of the current outages, assess operational i
readiness, and resume safe, reliable operations. The IMPACT Plan will be modified to assure the following objectives are addressed:
i 1.
Establish management control and oversight for the current Salem shutdowns to manage the outages safely including:
l
- sequence of the units to be restored
- control of work on each unit
- minimizing operator challenges
- outage oversight and shift management
- prevention of events
- shutdown risk management
- outage schedulmg I
i 2.
Achieve and maintain a high state of equipment reliability by defining criteria for determining system performance improvement (including performance measures to verify acceptability) in terms of :
i
- maintenance backlogs
- engineering backlogs
-PMs
- design changes
- operator workatounds
- operability determinations / deficiency reports
- incident reports / problem reports
- control room indicators
- system readiness reviews 3.
Assure that IMPACT Near Term Action Plans are completed within the outages, including any changes to the plans needed to improve management and process performance.
4.
Define the program and processes to be used to assess plant readiness for startup and to manage the startup and power ascension of the units.
t 5.
Establish and implement an integrated plan and schedule to manage the outages and restore each unit to power operation.
e h
)
d 1
i
gg gy:
6-S-35 : 4:51PM :
PSE&G LIC & REG 6103375354:s 4/ 4 i
l I
SCHEDULE:
(
l The schedule for development of the additional IMPACT Near-Term action plan and restart actions is as follows:
l Item 1:
Complete by Friday, June 23,1995 ltem 2:
June 30,1995 Item 3:
Prior to Startup item 4:
July 15,1995 1
Item 5:
July 15,1995 Scope Review Meeting with NRC:
Proposed to be by 6/30/1995
\\
Restart Review Meeting with NRC:To Be Determined i
i l
4 I
~
SENT BY:
6~12-35 ** 3:26PM ;
PSE&G LIC & REG 6103375354 s 2/ 3 58'"
P 'l l.
SALEM UNrr2 REACIOR TRIP JUNE 7,1995 SIGNIFICANTEVENTRESPONSE TEAM A Signiscant Event Respons. Team (SERT) is assembled in re-st.;e wi th NC.NA-AP.ZZ-0061(Q) (Signiscent Event Response Team Managemsat) to satisfy PSEA O's commaments and FSAR requirements for conducting independent assessmcats of selected pla er trends. Events or trends warranting SERT invesdgetions are determinednt operati{
byeither a station seeeral manager or a Nuclear Business Unit departmast vice president.
The SERT is a team of experienced personnel sww to independently i westigata events of concern. The Salern Unit 2 reactor trip ofJune 7,1995 is such an event. The current te SERT 9542 was charted on June 8,1995 by the General Manager - Salem Oper consists ofthefollowingmembora:
SERTManager Mark Shedlock Manager-Nuclear Prxurement end MaterialMget.
Member Pete Ott NuclearTraining Caru Member Scott Ward ar Salem Quality A ss. e Member WilliamLowry Salem TechnicalDepsrtment Member KenMoore Onsite SafetyReview - Salem Member Kumar Sarkar NuclearEngineering r+g r,t Member Dave Rotivook NuclearFuels Member Bruce Smkh SalernTechnicalDepsrtment Mornber Jack Arager-INPO Assistance-Events AalysisEvahmtor The general objectives of the SPILT process are to:
Idend$ root canses, causal t utors, inappropriate sedons and inadequat e
elled barriors.
Identi$ recomroendations fbr short and long term corrective actions to yevent the event from recurnos.
1 Speci6caBy, SERT 95-02 is charted to W. an indepedant review and u circumstances of the reestor trip includies the iblowing:
sessmers ofthe t
Review the preparadons fbr removal of the unit oom service, m' eloding l
activities daring that tiene period.
Review the organization's perfbrmance in assessing the operability of 28 and 22 firam ti:ns ofproblem identification until problem resolution following u6it shutdown Perform an independent assessment of the root cause detenninstione pe e
staffragarding theplant trip.
Develop a sequence of events and caussi Ibetors chart and identify failed
- barriers, Aseses the sa8ny signi6eance of the mat.
e l
compare the actual plant response to the aniscipsand response per plant
'sesian.
SENT BY:
6-12-85 ; 3:27PM :
PSE&G LIC & REG-6103375354:s 3/ 3 s
l 9
Assess operator response prior to, during, and subsequent to the event ending at cold e
shutdown.
. Assess the use of Operating Experience Feedback (OEF).
Assess the response of the organintion to the requirements of the E-Plan.
From the above rwiew, a uniform and compida.dve report will be developed that includes ' root cause determinations and corrective action reco==a-Mons.
% 2 M h;w JL) 6h&T SERT Manager Date General Manager-Salem Operations Date l
l The SERT team expects to conclude its investigation and provide a Snal report by June 29,1995.
i l
l l
e N
]
June 23,1995 dj Salem Unit 1 has restart priority j
1 $s3 Following a review of outage scope for
- Nuclear Fuels can support this option d M.
both Salem units, restart priority has been and when the schedule is finalized, i
given to Unit 1. The decision was announced plans can start for core design to yesterday in an FYI from John Summers, support operating periods; and i
GM Salem operations.
. known critical path activities for both "The prudent action is to start Unit I units were reviewed to determine the i
refueling at this time and incorporate restart total combined outage months issues mto the schedule as the review process needed to restore both units to ser-4 is completed," Summers wrote. "The Salt.m vice. This time is reduced by com-Restart Plan, an addition to our IMPACT pleting Unit I activities first. The i
Plan...will be our road map to successfully amount of total outage time for both restarting both units."
units impacts the Nuclear Perfor-l According to Summers, major factors mance Standard and, as such, will supporting the decision are:
affect replacement power costs.
}
= 1R12 outage sche'dule development is "As stated previously," Summers l
close to completion and the critical continued, "our primary objective is j
corrective maintenance items identified always the safe, reliable operation of the during the forced outage review are plant. This decision, and the continued 1
incorporated into this schedule; work of the management task force j
which is defining the scope of work The Bottom Line neceSSary to improve equipment Plant stats obtained from reliability in both units, supports our Daily Status Reportr g al of safe, reliable operation. In (See Unit 1,page 2)
Salem: Unit 1: forced outage i
a 737 Plant undate j
Days of Event-Free Operation - 37 s-Unit 2: forced outage No. IB diesel generatorjacket water repairs have been completed Days of Ev n -Free Operation = 16 at Salem Unit 1. The diesel and the Hope Creek: 100%,1,085 Mw No.12 charging pump will be restored to operable status today.
Days of Event Free rs ion = 25 No. I1 auxiliary building supply fan
,,O Peach Bottom 2: 100 %,
1.142 Mw on hne 245 dan repairs will be completed today.
Peach Bottom 3:
83 w; end of fuel No. 23 chiller motor replace-on line 89 dan ment and No. 21 chiller trouble-i i
Peak shooting activities continue at Unit j
Yesterday's PSEG peak 6,274 Mw
- 2. No. 21 residual heat removal Q
Today's stimated peak 6,057 Mw (RHR) loop will be restored to i
Stock available status today. RHR loop l
DPSNS 27-7/8 operability determinations continue
+1/2 l
at both units.
~ ~*~".
i m..
. _ _ _ _ ~, _., _
NUCLEAR TODAY Pcgo 2 w
Tcam to solvo matarial supply issue
% ; g y
The entire area of material titeN for o [i$ atioIto- '
E attemate), George Depta, Pete availability is being examined in Kordziel(Jack Hart, altemate)
Herb stiles. editor, ext.1004 an on gomg effort to improve Michael Moriarty and John FAX: 3391489 NBU performance.The Material Samson. Ed Titus of Nuclear ht/c Nos or via e. mail Availability Problem Solving Professional Services is provid-Team, ajoint effort between ing independent oversight.
Alternative ratemaking Materials Management and Station Planning, was formed Unit 1 gets final approval June 15.The team is charged (Continuedfrompagel)
Thanks in part to employees with identifying problems and determining where our priorities who contacted their state legisla-l 4
associated corrective actions in lie regarding the Salem units, we tors, the New Jersey State current processes to supply are taking the first step toward Assembly gave final approval to i
materials to the stations, bringing both units back on-line attemative ratemaking legisla-The team views this chal-and keeping them running well." tion that previously passed in the lenge as an opportunity to deal A separate FYIissued Senate. The Assembly approved with material process issues, real yesterday by Leon Eliason, the measure this week by an and perceived. The team's CNO and president-NBU, noted overwhelming 61 to 11 vote.
4 objective is to identify immediate the Salem units are not included Larry Codey, PSE&G and on-going actions necessary on the current NRC " Watch president and chief operating 4
to supply materials and services List." He wrote, in part, "I feel officer, had encouraged employ-j to support client needs for sched.
this latest development shows ees who live in the state to uled and emergent activities.
NRC confidence in our resolve contact their representatives and A goal-oriented approach to to better ourperformance, but it urge them to vote in favor of the improving this multi-departmen-is not time to reduce or case up measure.
tal process is being used and will on our improvement actions...we He says the newlegislation involve those groups that are will be measured on our results, gives PSE&G the opportunity to required to implement action not our promises." He reiterated, effectively respond to the new items developed by the team.
"we have reached a crucial competitiv realities of the Additional near term improve-M, ture at Salem station. This is energy marketplace.
ment action items will be inte-(
oportunity to start fresh-PSE&G and other utilities grated into the existing IMPACT 1 9 problems in the station, strongly supported the bill, Action Plan. Accordingly, a local
... Lea, start up again and keep stating that such legislation 1
area network ID, the units running well. I am would reward all consumers by NBU. SPARE. PARTS. TEAM, has convinced that with your contin-reducing overall costs. Regu-been established to solicit input ued help, we can doju;t that."
lated energy providers have long from anyone who has construc-argued that the existing legisla-tive ideas for consideration.
tion allowed non regulated 4
(Access instructions: you'll find Birthday meeting competitors unfair market the ID under the street talk Canceled advantages and placed New addresses for Lists. Use this list ID or any one of the team mem-Joe Hagan's birthday ersey in a diflicult competitive ber names to forward your communications meeting Position with other states that Monday moming June 26 has have approved similar refonns.
comments, opimons, etc.)
Bob Burricelliis the team been canceled. Anyone Codey repeatedly stressed scheduled to attend should the importance of the new law, sponsor George Sayeris team
'eader. Members are Glenn attend the meeting set for and was pleased with the over-Friday, June 30.
whelmmg Assembly approval.
Dames (William MacIntyre,
6 1
l l
1 FYI May 17,1995
\\
l FROM:
John C. Summers General Manager-Salem Operations -- ' -------------
SUBJECT:
UNIT 1' SHUTDOWN" As you know, a recent equipment failure in Unit I led to shutdown of the unit titis,
morning. I want to make clear to all NBU employees that actions taken by station personnel to take the unit offline were appropriate and just. This event is an example of the conservative decision making which we have emphasized in recent months.
Several steps led to the decisibn to sh$t down the unit:
e.-
On May 14, the No.13 switch gear room supply fan motor failed. No.12 fan e
has been out of service due to mechanical failure of motor bearings since December 1994. Only No.1I fan remained in service. Unit I was held at 60 percent power pending resolution.
The Switchgear Penetration Area Ventilation System (SPAVS), which these fans are a part of, is designed to maintain air temperatures that surround structures, systems, and components in certain areas of the plant. The fans do not come under Technical Specification (Tech Spec) requirements. However, the components to which they provide cooling do.
On May 16, system engineering determined that temperatures were satisfactory to maintain the structures, systems and components in the unit. Power ascension began. A review ofoperabilityjustification continued.
On May 17, the Operations Department took the assertive position of calling to closure any questions surrounding the system.
Upon determining that the appropriate level ofjustification to support operability could not be produced in a timely manner, the station conservatively declared the components in the switch gear rooms inoperable.
This placed the Unit in a Tech Spec requiring a shutdown last evening. The unit was manually taken offline at 2:02 a.m. this morning.
A Significant Event Response Team (SERT) is being developed to take a clear look at activities leading up to and including the plant shutdown. The team will review two areas:
Whether the station recognized the significance of the loss of redundancy in cooling capability for the switch gear in December upon loss of the first fan.
The timeliness and adequacy of engineering support provided from the time of the second fan failure on May 14 to the decision to shut down the unit in May.
h
l c.
f.
't Station personnel inade a decision to shut down the unit, based on the information made available to them. Management whole-heartedly supports that decision. As such, the decision to shut down the unit should not and will not be considered as a basis for re-zeroing the " Days ofEvent-Free, Operation" status, board.
1 Salem management will consider the two SERT areas mentioned above when reviewing event-free status for Unit 1.' A decision on the unit's event free status will be made and communicated by Thursday, May 18.
1
.. t 1
Also subject to further review is the scope of work assigned to this forced cutage. We must ensure we do whatever work is required to sup;iort a dependable run to our planned September outage. When the scope is finalized, it will be communicated to the organization.
. c,....
+
') i, e f.' $ (G i. ! j l4 g++. f*
r?. ' r't
- .}
/
e' *1 ijt.
4 j '
4 9.
.t e
g'
(*
.s,. s to ' :* lic e ;'l ra e
- i t
i
.r*
l
', i
p.,
a i.
ee.*
gw gt
- 't w p i
a e- ),.f ti
., i,..'.r.
8 ja;il a
- d i'
.r* (.
i,i
'. e-
.;j t
s',,
(1-
.I*
4 *
- i f
- y '
.l e
rt ;:
i:
v
. i-
+
,h f
'I s
','D e
,9,i,
t e
- 5 i, * {
.I e
3,,,
1
r" t
I e
,,}.
s').
p.t ij ;*
b *.,,. i 1'
O e.
e
\\
O PSI 6G~
~
i 4
Nuclear Business Unit ~
~
Employee Update f
May 19,1995 New Engineering Intervention Organization to Focus on j
Improving Salem Engineering Support As identified in our IMPACT Plan, engineering support of the stations is a high priority focus fo key factor in assuring that we understand our equipment problems, develop effective tec i
operations in making operability determinations. The May 17 forced outage at Salem Unit I and othe have indicated we need to take immediate actions to strengthen these functions.
To address these immediate needs, we will re-focus engineering support under a new Sale Bruce Preston. Bruce will be responsible for the system engineering group and a new, Sale sup. This new ES group will be staffed by 30-40 engineers skilled ar.d experienced in design j
and component expenise. Reporting to Bruce will be Jerry Ranalli, who wilt head the engineerin Mike Rencheck, who willjoin the Nuclear Business Unit May 30. Mike will head the system engin the group. Over the next several days the group will be staffed with employees from existing en suppon, QA/NSR, licensing and other support groups. On Wednesday, May 24 they will begin perfo i
following functions:
operability determinations and safety malyses; e
identifying known equipment problems and system vulnembilities; e
prioritizing and managing associated risks; and e
developing effective technical solutions to equipment problems.
e In addition, the Engineering Support organization will assume the non-System Engineering functions fr Technical Services organization. This will allow us to re-focus on System Engineering to pro 3
level of performance and support to operations.
I i
Under this engineering intervention concept, design engineering will re-focus on design chang ownership and ongoing nuclear engineering problems. Any engineering positions left vacant because of add team will be filled to meet required outage support.
1 i
l This action is being taken to provide an immediate improvement in engineering suppo l
intervention actions are identified, we will make changes as l
l Leon Eliason CNO and President v
4 i
1 w
l u t,,,
u_;_
u,
- 7 MAII. SLIP l^O PSEG 3
JoS -
SAM -
.f THF -
Nuclear Business Unit Employee Update m 2a a May 19,1 -
New Engineering Intervention Organization to Focus on Improving Salem Engineering Support As identified in our IMPACT Plan, engineering support of the stations is a high priority focus for improvement. It i key factor in assuring that we understand our equipment problems, develop effective technical solutions and suppor-operations in making operability determinations. The May 17 forced outage at Salem Unit 1 and other recent events have indicated we need to take immediate actions to strengthen these functions.
To address these immediate needs, we will re-focus engineering support under a new Salem engineering manager, Bruce Preston. Bruce will be responsible for the system engineering group and a new, Salem Engineering Support ES) Group. This new ES group will be staffed by 30-40 engineers skilled and experienced in design basis, licensin basis and component expertise. Reporting to Bruce will be Jetty Ranalli, who will head the engineering support function and Mike Rencheck, who willjoin the Nuclear Business Unit May 30. Mike will head the system engineering function of the group. Over the next several days the group will be staffed with employees from existit-engineering, technical suppon, QA/NSR, licensing and other suppon groups. On Wednesday, May 24 they will ber performing the following functions:
operability detenninations and safety analyses; identifying known equipment problems and system vulnerabilities; e
prioritizing and managing associated risks; and e
developing effective technical solutions to equipment problems.
e In addition, the Engineerire Sup9on organization will assume the non-System Engineering functions from the old Technical Services organization. This will allow us to re. focus on System Engineering to pmvide a further improvec level of performance and support to operations.
Under this engineering intervention concept, design engineering will re focus on design change packages, design basis ownership and ongoing nuclear engineering problems. Any engineering positions left vacant because of additions to the team will be filled to meet required outage support.
i
MAY-22-1995 09:40 FROM PSERG EXTERtA AFFAIRS TO 99353741 P.02 This action is being taken to provide an immediate improvement in engineering support to the station. Our IMPAC Plan actions will continue to be implemented to defmc long term solutions to engineering support issues. As other intervention actions are identified, we will make changes as appropriate to the IMPACT Plan.
l Leon Eliason CNO and President
)
1 i
i TOTAL P.02
?
l GeneralManager Salem Operations 1
)
i 1
l TOPIC: Unit 1 Update June 7,1995 t
i Three weeks into this Unit 1 forced outaae,being done.I'd like to review the scope
'he importance we are placing on the woTr
'irst of all, I must re-emphasize that we are approachin this outa fifferent mind set. This means we are workmg the righf things an$e with an entirel 4
ack with a reliable plant before we consider starting up. Our attitude has to be, fix verything that needs to be fixed for reliable operation and then come back to power.
we have conducted a multi-discioline review
.i addition to necessary maintenance work,lity determinations operator work aroun
-f o maintenance issues such as operabi j
i
.nd blems with control room indicators. This review enables us to aggressively go fte the problems that present the greatest challeng,es to event-free opedih'on of the plant.
he maintenance issues identified liave been priorrazed by the Salem system managers 4
ad other members of the Salem management team. This review has provided us with a i
1 acused list of priority items needed to support the return of the unit.
j I
we are targeting a unit retum date ofJuly 5. This date
.iased on our review,d challengmg schedule. In order to meet this schedule,p eith an aggressive an it requires nat we take an aggressive approach to work with the proper urgency to ensure closure of l
ritical component windows. Plant safety and resource reauirements have been given the i
anast consideration in making this schedule. Some disciplines - articularly 12e 4
,ontrols. group - will face greater challenges due to the amount of! heir workload. We
. ire seeking additional support by others, such as Hope Creek and Operations Services, to augment ourresources.
I will bortant for all members of the Salem team to understand the focus of this outag t is im e strong teamwork and impressive communications to meet our aggressive i.e. worFmg the right
';1tes. All of our efforts must be focused on our highest priorities,t tak,es to have rehable 4
obs at the ri time. Our actions demonstrate were domg what i i
ower throughout the summer months taking us up to the refueling outage in i
ept
. We will not return the unit to power until we're positive we've done the right
,ings to have a reliable run.
1 1
1 1
i n9E01199E 'ONRO:ll 1S/r0:ll 96,10 '90(02.0 996 HEE--609 SN01.1.VHido X31VS K0 013Sd K0Hd l
4
4 l
I 8
l GeneralManager
}
Salem Operations i
3 i
l TOPIC:
Unit 2 Forced Outage June 8,1995
)
Salem Unit 2 is currently in Mode 4, with an expectation to enter Mode 5 (cold shutdown) tomorrow. Manual shutdown of the unit began at 6:28 p.m., June 7, to correct operability problems in the residual heat removal (RHR) system.
I When the turbine was taken offline shortly after 11 p.m., a breaker failure in the 500Kv j.
yard resulted in the loss of several electrical busses. This resulted in the loss of two
{
reactor coolant pumps and a subsequent reactor trip. Because of ongoing maintenance and the configuration of the busses, the normal station air compressors were lost. Station i
air needs were met by diesel-driven temporary air compressors and the two emergency
)
control air compressors.
I j
Other components were affected by the breaker failure. Because power to the house-heating steam boilers was lost, auxiliary steam was not available. Since number 23 and 24 reactor coolant pumps were out of service, normal pressurizer spray was reduced.
l Because effective spray capability was lost, operators switched to auxiliary spray. Their timely actions maintained pressure control and kept power relief valves from actuating.
Work continues in the 500Kv yard. The 2-10 500Kv breaker was already cleared and tagged, which caused the cross-tie line between Hope Creek and Salem stations to open.
Several station power transfonners were de-energized by this tripping. At this time, we are expected to have the switchyard operational by 4 p.m. today.
4 i
As always, our primary objective is the safe, reliable operation of the plant. We will complete all necessary maintenance for safe, event-free operation before re-starting either i
unit.
)
i l
1
t O PSEG
~
f I
Nuclear Business Unit i
Employee Update
[
June 9,1995 j
Salem's Challenge Presents Opportunity For NBU
]
We have reached a crucialjuncture at Salem Station, a tuming point in our history. All NBU employees will be l
affected by the events of the past few days and, more importantly, what actions we choose to take in the future.
We must view this time as our opportunity to start anew by finding the problems, fixing them, starting up again t
i and running well.
Two months ago, our IMPACT Plan marked a commitment by the organization to raise its standards for safe and reliable operation of our nuclear units and to be accountable for results in accordance with those standards. My decision yesterday to keep Unit 2 off-line until the appropriate maintenance was completed, and the prior decision on the Unit I outage, is a continuation of that commitment. No longer will we only fix what is broken
{
and restart the unit, only to have it come down again.
I spoke yesterday with Tim Martin, NRC Regional Administrator. Iinformed him of my decision to keep both l
units off-line until the maintenance necessary for safe, reliable operation is completed. We will not re-start the units until we are satisfied we can do this. The NRC has agreed that we will take the lead in our actions to restore the plant to event-free operation.
As a result of this decision, Region I will not send an Augmented Inspection Team. They plan to supplement their existing inspection staff on site because of all the work we have ahead of us. We expect to receive a Confirmatory Action Letter from the NRC, with the following stipulations which we have agreed to:
- 1. complete the SERT review of reactor trip circumstances;
- 2. appropriately address long standing equipment reliability and operability issues;
- 3. after defining work scope and approach to the outages, meet with the NRC to discuss these plans;
- 4. after the work is completed, conduct a restart readiness review to determine for ourselves the ability of each unit to operate in a safe, event-free manner, and
- 5. after the restart review, meet with the NRC and communicate the results of that review.
l These latest developments can be viewed as a setback or as an opportunity to move forward. We must change j
our processes and procedures so that maintenance problems, operator work arounds and other issues that have challenged us in the past will be addressed differently. But more importantly I see our situation as a turning point, where we can turn around the most important human elements of our operation - our focus, our priorities, our
l morale. As a member of the NBU, you are the crucial key to our successful turnaround. There is no tima to stand
{
idly by and see what happens. We all must get involved to secure ourjobs and our futures.
I will hold several meetings next week to personally pass on this message to as many of you as I can. The same message will be communicated to the entire NBU in subsequent meetings held by my CNO team. Don't be afraid to ask questions or speak your mind.1 am very interested to hear your views. But remember, this is not the time to point fingers or to place blame. By working together we will restore these units to successful operation.
1 CNO and President l
4
t OME NuclearBusiness Unit i
t Employee Update f
Joe Hagan j
Vice President - Nuclear Operations June 9,1995 3
i Salem Task Force Established 4
i 4
)
This FYI is to inform the organization that I will be leading a management task fon:e j
necessary to improve the equipment reliability of the Salem units.
1
)
We will not restitt either unit until we are assured that the units will operate safely an necessary changes to maintain the units in prime conditions for our operating depart charter for these efforts, for your information.
i i
j 1
ryone must remain focused on maintaining the plants in a safe shutdown condition.
the units in this safe shutdown mode until we have completed the work necessa j
i l
The first priority is to determine which unit will receive the focus for initial restoratio i
the units one at a time.
As our plans are formulated and defined, we will keep you informed so you will be aware l
the units.
i
+_
\\
- 1 l
O PSEG Nuclear Business Unit Employee Update f
June 12,1995 Employee Meetings, " Communications Stand-down" to be held As I have said before, Salem station is at a turning point. I want to meet face-to-face with as many NBU employe l
possible to discuss the urgency of this situation - to rally the support of all NBU employees by getting you involved in
)
turning around Salem station. The first step is communicating with all employees: where we are, what led us to this l
point, where we're headed and most importantly, what is expected of NBU employees during this time.
In order to openly communicate the current status of the Salem units and our future actions for improvement, several employee meetings will be held throughout the NBU in the next two days. I will address a cross-section of employee two meetings tomorrow at the Processing Center, one at 9:30 a.m. and one at 2:00 p.m. A request was made of R/C rrmagers today, through Voice Mail, to allow some of their employees to attend these meetings.
NBU employees unable to attend one of those meetings will receive the same information on Wednesday morning d a " Communications Stand-down." Using the concept of a safety stand-down, all NBU personnel who are able to, will stop work from 9:30 a.m. to 10:00 a.m. Wednesday, to attend a meeting at their location. Members of the CNO team will roll down to their organizations the same information communicated by me in tomorrow's meetings.
1
" Communications Stand-down" meetings will be held as follows: I will address employees in the Nuclear Administration Building (NAB) cafeteria; John Summers will address all available Salem station personnel in the Salem cafeteria; Mark i
Reddemann will meet with all available Hope Creek personnel in that station's cafeteria; Joe Hagan will address employees working in the Nuclear Operations Services Facility in the multi-purpose room and Jeff Benjamin will meet with all Material Center personnel in the training room. Employees working in the Processing Center not able to attend l
one of the Tuesday meetings will be asked to come to the NAB meeting on Wednesday. I will go out to the Nuclear l
Training Center (NTC) on Wednesday afternoon at 2 p.m. to speak with NTC employees. Arrangements will be made to hold a meeting for Salem station back-shift employees, led by Summers.
It is important for all employees to know - we have no set schedule for returning the plants to operation. We will continue to work the known work and will determine the total scope of the work we have to do. Based on our plan, we will develop a work schedule and we will aggressively work that schedule until we reach the point where our units l
are ready to come back on-line.
CNO and President l
l l
o
~
i' Communications Plan i
Specific work orders and components will be discussed with the NEOs by the NSS at the shift briefings. Any other work encountered during their rounds should be brought to the shiR supervisor's immediate attention.
Twelve-hour status update on identified critical equipment and activities will be l
l conducted at the SNSS meetings at %30 and 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br /> daily Lead team members from each group will provide details to the team leader prior to the meeting.
l.
Managers will be updated on progress at 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br /> during weeckdays.
1 l
l l
l l
l i
I i
i i
I
i FI Operations Manager - Salem June 15,1995 The Salem Umkwill be placed in a work standdown condition until cenain systems and components are retumed to operable status. Some of the key components involved in the effort will be the IC Diesel Generator, the RHR loops, and the filling and venting of the RCS loops. A multi-discipline team is being assembled under the leadership of Brian O'Grady and Phil O'Donnell. The purpose of this team will be the continual assessment of the condition of all safe shutdown equipment and the restoration of degraded components to an acceptable level.
This team will be focused on two major areas in the short term. The first item is to take immediate actions to protect all safe shutdown systems from further challenges.
The second step will be to implement corrective actions to stabilize the plant,in'a cold shutdown condition. Personnel should pay particular attention to any work they are performing to ensure that it will not adversely affect the condition of the unit during this time. Work will be restricted in some key areas, such as the Switchyard, Relay Rooms, Service Water and RHR areas. Any work in these areas must be specifically authorized by the SNSS.
Contingency actions and plans for critical components are being developed tonight.
The organization, recovery plan and conununications plan will be issued tomorrow morning to all organizations.
l l
FI Rev1 Operations Manager - Salem June 15,1995 The Salem Units will be placed in a work standdown condition until certain key systems and components are returned to operable status. Some of the key components involved in the etTort will be the IC Diesel Generator, the R11R loops, and the filling and venting of the RCS loops. A multi-discipline team is being assembled under the leadership of Brian O'Grady and Phil O'Donnell. The purpose of this team will be the continual assessment of the condition of all safe shutdown equipment and the restoration of degraded components to an acceptable level.
This team will be focused on two major areas in the short term The first item is to take immediate actions to protect all safe shutdown systems from further challenges The second step will be to implement corrective actions to stabilize the plant in a cold shutdown condition. Personnel should pay particular attention to any work they are performing to ensure that it will not adversely affect the condition of the unit dunng this time. Work will be restricted in some key areas, such as the Switchyard, Relay Rooms, Service Water and RHR areas. Any work in these areas must be specifically authonzed by the SNSS.
Contingency actions and plans for critical components are being developed tonight.
The organization Shutdown Safety Assurance Team plan and conununications plan will be issued tomorrow morning to all organizations.
l i
_ _ ~
UNIT SHUTDOWN CONTINGENCY ACTIONS SlHFT REVIEW OF ABNORMAL OPERATING PROCEDURE FOR LOSS OF e
RHR (COMPLETED BY EACH SHIFT)
DAILY CALCULATION AND LOGGING OF TIME TO CORE BOILING e
(COMPLETED BY EACH SHIFT)
INCREASED OPERATOR (SRO/NEO) WALKDOWN OF RHR, EDGs, AND RELAY ROOMS. TO BE PERFORhED TWICE PER SHIFT AND LOGGED IN CONTROL ROOM NARRATIVE.
WORK STANDDOWN EXCEPT THOSE ITEMS NECESSARY TO RECOVER SAFE SHUTDOWN EQUIPMENT, SURVEILLANCE WORK, ITEMS CRITICAL TO CURRENT PLANT OPERATION AS DETERMINED BY OM,OE,SNSS, OR SHIFT SUPERVISOR. (COMPLETED)
SECURITY GUARD PLACED AT SWITCHYARD GATE TO CONTROL e
ACCESS TO SWITCHYARD. SNSS APPROVAL REQUIRED FOR ENTRY (COMPLETED)
BOTH CONTROL ROOMS WILL BE MANNED FOR MODE 1 OPERATION e
i EVALUATION OF SALEM UNIT 1 RCS FILL AND VENT IN ORDER TO PROVIDE HEAT SINK IN THE EVENT OF A TOTAL LOSS OF SHUTDOWN COOLING l
1 e
1 O PSIKi
~
Nuclear Business Unit t
l Employee Update f
f I
August 10,1995
]
Simpson Announces Director Positions in. Nuclear Engineering
{
Since arriving in the Nuclear Business Unit, I have been familiarizing myself with the Nuclear Engineering organization. One message has been clear: in our effort to improve operational performance in the NBU, we must continuallyimprova our support to the plants. I am announcing today the addition of two j
director positions in the Nuclear Engineering organization which will report to me.
l David F. Garchow willjoin the NBU as director - system engineering on August 21. He will be 4
responsible for system engineering across the site. David comes to us from Palo Verde Nuclear Generating a
i Station in Arizona where he was director ofsite technical support in the System Engineering Division. At that
. plant he was also managcr - mechanical / performance engineering, manager - fire protection support, iupervisor - refueling services, shift technical advisor and plant operator.
David has a senior reactor operator's license at Palo Verde and also holds a bachelor of science degree i
from Michigan State University.
j Also joining the NDU will be Gary J. Overbeck as director - design engineering. He will be responsible for design engineering in the NBU. His tentative start date is September 5. Gary has more than 26 years of engineering and project management experience. For the last 15 years he was vice president and I
general manager of the northeast region and national technical director at Ogden Environmental and Energy 1
Services Company in Blue Bell, Pennsylvania. He has participated in numerous utility and NRC-sponsored inspections as the mechanical / nuclear design area leader. He was a member of the Integrated Design j
i inspection teams for Byron, River Bend, Perry and Shearon Harris; and the Independent Design Verification Program review teams for Limerick, Hope Creek and Clinton. Gary also held several positions in his six years with United Engineers & Constructors (UEC) and spent five years in the Urdted States Navy.
Gary has a bachelor of science degree from the U.S. Naval Academy with a certificate in nuclear reactor theory and operation. He is a registered professional engineer in Pennsylvania and a member of the American Nuclear Society.
M *d Pt140 S66T-TT-OnO
,i
a u-
--.a l
- d "10101 The responsibilities of those Nuclear Engineering memb:rs who currently perform similar functions in design and systems engineering are being assessed. In the coming weeks, there are issues to be finalized and l
j adjustments to be made as we re-shape our organization to meet the needs of the plants. I will be meeting with you as we make these changes so you completely understand why they are being made and the important I
role you have in our success. Pleasejoin me in welcoming David and Gary to our organization and give them your full support.
l YI l
l Senior Vice President - Nuclear Engineering l
i i
l I
i I
l l
l E0*d PT 2.0 S66T-TT-Ond
AUG-17-1995 07159 P.01 6
1 U,' ODM M M.) ld K
?
OME I
NuclearBusiness Unit Employee Update f
i August 15,1995 Large-group meetings to be held in Nuclear Operations I
Sincejoining PSEAG and arriving at the Salem / Hope Creek site, I have met inform l
departments in the Nuclear Operations organlation. To expedite this introductio to hold large-group meedags with employees ofNudear Operations on August know what my expectations are ofyou.to meet with as many ofyou as po To accommodat' this large group of people, five meedngs will'be held in the fire s
Jperations Servloes Facility. The meetings will be on August 16 and 17 et 12:00 a Wgust 18 at 9if6TdChiy direct reports have received infbrmatlos concerning h each group should attend each meeting.
At a later date,'I also plan to meet with ernployees of the r=alatne NBU depa to share with the entire organlation the direction I plan to take Nuclear Operati to achieve oursoals.
Leon Elisson has communicated to you many times before that you are the key to t how I envision this organization doingjust that and impr Ye.af}
Senior Vice President - Nuclear Operations i
so a ee,es cus as ee Woud TOTAL P.01
?
O PSEG
~
~-
Nuclear Business Unit i
Employee Update f
f June 22,1995 NRC " Watch List" Released Today 1
Every six months, the Nuclear Regulatory Commission (NRC) evaluates all nuclear power plants to determine whether their performance warrants being placed on the " Watch List" - a list of plants with performance problems the NRC closely monitors. The current Watch List was issued today by the NRC and the Salem units were not included.
i 1
As you will recall, senior NRC managers met with the PSE&G Board of Directors in March to voice their concerns about declining performance at Salem. The NRC decision not to place the Salem units on the Watch List indicates that j
the message given to the Board of Directors was received and is being appropriately acted upon. But we will be i
measured on our results, not our promises.
I feel this latest development shows NRC confidence in our resolve to better our performance, but it is not time to reduce or ease up on our improvement actions. Since the shutdown of Unit 2, the NRC has taken enforcement measures such as the Confrmatory Action Letter, which increases NRC oversight of our work. As a result, their on-site staff will probably be expanded. In the months ahead and when Salem gets close to restart, we may also be subject i
to increased NRC team inspections.
I Performance issues at Salem Unit I and Unit 2 have been addressed through the NBU Issue Management and 4
Prioritized Action (IMPACT) Plan and will continue as planned. Our goal is still to " find what's wrong and fix it."
Challenges such as operator work arounds, work order backlogs, operability determinations and preventative a
maintenance remain as priority items during this outage time for the Salem units.
The recent NRC actions mean one thing to NBU employees: continue our course ofimprovement actions. Our roles remain the same. We must stay active and involved to secure ourjobs and our futures. As I stated on June 9, when I announced my decision to keep both Salem units off-line until appropriate maintenance is completed, we have reached I
a crucialjuncture at Salem station. This is our opportunity to start fresh - find the problems in the station, fix them, start up again and keep the units running well. I am convinced that with your continued help, we can do just that.
2 l
CNO and President i
ME T N gM A MQ M'%
Ch Mi1 CHARTER h
d Q kq, Salem System Readiness Reviews E R kl L h-g OBJECTIVE:
To provide an independent evaluation of the comprehensiveness and quality of PSE&G's efforts for system readiness reviews and present the inspection l
results to the Salem Assessment Panel (SAP).
i SCOPE:
For a selected system / technical area, based on the inspector's knowledge and expertise, verify the thoroughness of licensee efforts to evaluate and present to site management [i.e., System Readiness Review Board (SRRB) and Management Review Committee (MRC)) the system readiness review results. This review shall indirectly validate the adequacy and effectiveness of PSE&G Procedure l
SC.TE-TD.ZZ-0023(Z).
METHODOLOGY:
- Select a system for review.
Observe SRRB/MRC meetings during week of 8/14/95 at site to become acquainted with conduct of business including: detail level of information provided, questioning level, robustness of database, and the acceptance thresholds of SRRB and MRC.
Conduct onsite and in-office independent inspections (weeks of 8/21 and 8/28) to gauge the scope and effectiveness of licensee's review. Evaluate the effectiveness of licensee process and decision-making by assessing the rationale used to determine issues / items that are considered for restart and those items that are deferred. Compare restart items / issues against NRC open issues list; identify differences to SAP for resolution.
Review System Readiness Review Report (for selected systems) using a vertical slice performance-based approach, including independent verification of the following:
- SSFI (licensee-performed) Open items
- Salem Design / license basis
- NRC open item review (incl. QA assessments, dept assessments, NRC)
- Workarounds
- Planned modifications including status of temporary mods.
- Work orders
- Deficiency reports
- Adequacy of procedures for testing, inspection, and maintenance Spare parts
- Availability of spare parts
~
Exit with licensee (8/31, by phone) after comparing observations internally (8/28-29/95).
l b
I
2 Perform plant walkdowns to verify integrity of seals, equipment and I
material conditions, tagging, etc. (include drawing usability).
Address industry info including GLs, ins, Bulletins, Westinghouse i
Interview operators and system managers.
e l
Observe SRR8 and MRC meetings (for selected systems) and integrate with e
vertical slice review.
Integrate inspection findings into an assessment of the comprehensiveness and quality of licensee efforts for restart readiness.
Present to SAP by 9/6/95 DRS REVIEW MEMBERS l
DRS Lead Selected System Availability Thru L. Harrison Units 1&2 125/250 Vdc and Batteries (9/23)
S. Chaudhary Units 1&2 Diesel Generators (8/30)
- 8. Welling Units 1&2 Auxiliary Feedwater (9/15) 50-272; 311/95-17 -- IP 92903-50 (RR) i PSE&G Contacts:
i Mike Rencheck (6C9) 339-1545; PSE&G Manager of System Engineering (Secretary:
Rene x2050)
Dana Cooley, MRC Facilitator (609) 339-7427 NRC
Contact:
Gene Kelly (610-337-5111) i i
-m i
l
e O PSEG Pubhc Service Elec:ric and Gas Com;ar P O Sex 236 Harcoexs Brecge New Jersey CS038 r
Salem Generating Station i
i TO:
Distribution FROhi:
Lee A. Catalfome Operations hianager - Salem
SUBJECT:
INFORNfATION DIRECTIVE 94-044 (SOD-94-106)
DATE:
November 11,1994
)
Attached is important information concerning Core Damage Awareness. The information on the charts was obtained from the Individual Plant Examination (IPE). You should become familiar with the information and ifyou have any questions, please direct them to your supervisor, an Operating Engineer or myself.
t i 1
Distribution:
All Operations Department Personnel
- 51. hforroni J. Summers J. hforrison T. Cellmer C. hiunzenmaier G. hiecchi J. Ellis
/
,, :...... ;a J
EVENTS LEADING TO CORE DAM AGE The pie chan assumes that core damage has occurred and indicates the es ents (initiators) which led to the damage.
The chan also is an indicator of areas where personnel may need to resiew infrequently performed procedures and areas that may need increased focus beyond the normal to mitigate the consequences of an event.
This is not unlike a chan that may show traffic fatalities for the year. Assume that we had 100 fatalities for the year and that 57.7% of these were related to alcohol and 19.3% of them were weather related. The most probable event leading to traffic fatalities is the use of alcohol. Alcohol and the weather are considered initiators.
The pie chart is sliced by events called initiators. These initiators are events which require or cause a plant shutdown. These events may challenge operators or safety systems. The events identified include equipment failures and other uncenainties in almost all cases.
Sometimes operator actions may prevent or slow an event without core damage but there are times that actions may not be completed or finished in the time expected. These can be i
caused by equipment malfunctions or events that occur that slow the actions being l
performed.
All the initiators have been analyzed and a frequency of occurrence per year has been assigned. There are some initiators that are not,incitided in these calculations and those are t
the ones that start from outside the plant such as plane crashes, fires, canhquakes etc.
INITIATOR EVENTSTEAR EXPLANATION Transient with PCS 5 12 Primary side transient Transient w.o PCS 0 16 Secondary side transient Loss of Off-site power &
0 06 10% of the 57.7% are a LOP Station Blackout (LOP /SBO) 47.7 % are LOP with a SBO LOCA STGR 0 03 SpecialInitiators 0 02 Loss of suppon system that stans transient.
Main SteamNeedwater Line Break 0.002 ATWS/ATWT 0.0005 Anticipated trcnsient w/o scram' trip Loss of SWS 0.000004 Loss of Service Water l
t ne l
The percentages shown in the pie chart for each initiator take into account the likelihood for core damage from the event and the frequency ofoccurrence.
i l
l Theretore an mitiator with a low frequency of occurrence, such as Loss of SWS, but with i
l l
a high likelihood of core damage can result in only a 2.7% contribution, but an initiator l
with a high frequency of occurrence, such as a transient with PCS, but with a low l
probability of core damage can result in a 12.9% contribution.
The chart is indicative of all events that could lead to core damage, and not the amount of core damage that could occur. Procedures are designed to combat the event with calculated equipment failing. The actual risk of core damage will increase >vith each additional piece of equipment that is removed from service.
The bar graph is an indicator of the importance of components and their impact upon the prevention of core damage. The removal of equipment compounds the possibility of core damage and its extent.
l The bar graph could also be used as a guide for prioritizing the return of equipment to service. The ones that are the most important (highest impact) should be returned first.
The example of this is an emergency diesel and a service water bay. Many of us may return the EDG first, but the bar graph indicates that the service water bay has more impact in the mitigation of an accident than the EDG. The support systems of a l
component should be returned prior to the equipment itself.
EXAMPLE: Assume that a 4KV sital bus and associated EDG are released to the Operations Department following maintenance activities, at the same time. The bar graph would indicate that the vital bus should be made operable before the
'g EDG. This is due to the greater impact to core damage probability the vital bus has over the EDG.
In the weeks to come an individual from Engineering Sciences Department will attend a shift briefing to answer any questions you may have on this document. Should you have a question on this directive in the interim please call the number on the bottom of the bar graph page.
i s
OPERATOR ACTIONS MOST I.\\fPORTANT IN l
t t
PREVENTING CORE DAMAGE 1.0 Transfer from ECCS injection to recirculation (in a timely manner)
(IAW EOP-LOCA 3 " Transfer to Cold Leg Injection.")
2.0 Provide alternate ventilation following a loss of Control Area Air Conditioning or Switchgear Room ventilation.
(IAW OP AB. LOOP 0001(Q), OP-SO.CAV-000l(Q),
OP.SO-PC-0001(Q) LOOP-0001 Control Room Air Conditioning, CAV-0001 Battery Room Ventilation, PC-0001 Switchgear rm. ventilation 1
(Rev. Req. initiated for switchgear alternate ventilation developement))
t 3.0 Isolation of non-essential CCW loads following the loss of I CCW pump.
(AB.CC-0001 performed concurrently with EOP-TRIP-1 and j
AB.RC-0004).
4.0 Initiation of Rapid Boration following an ATWS.
(IAW EOP FRSM-1 " Response to Nuclear Power Generation")
j
}
l 5.0 Remote Shutdown following the loss of the Control Room.
t (IAW AB.CR-0001 " Control Room Evacuation" or AB.CR-0002
" Control Room Evacuation due to fire in Control Room, Relay Room, or i
l Ceiling of 460/230V Switchcear Room" 6.0 Recovery of a Service Water Bay that was out for maintenance.
(IAW OP-DD.ZZ ODOS(Q)" Tris Tagging Operations" & OP-DD.ZZ-ODIO(Q)" Removal and Return of Safety Related Equipment". (In Draft) 7.0 Provide Diesel Generator Area Ventilation by opening hatch after a loss of l
ventilation.
(IAW SC FR-EO.ZZ-0001 " Control Room Fire Response").
The opening of the hatch was superceded by Emergency switches on RP5 pnl(s).
8.0 Initiation of Feed and Bleed (RCS) when needed.
(IAW EOP-FRHS-1 " Response to Loss of Secondary Heat Sink").
9.0 Manual Turbine Trip Following an ATWS l
(EOP-TRIP-1 " Reactor Trip or Safety Injection" & OHA F-39 "AMS AC f
Actuation").
1 10.0 Utilization of Condensate te feed Steam Generators following a loss of Aux Feed Water.
(EOP FRHS 1 " Loss of Secondary Heat Sink").
l
SALEM GENERATING STATION CORE DAMAGE AWARENESS EVENTS LEADING TO CORE DAMAGE Speclaf initiators LoCA/foTR:19.3%
(except SWS): 0.8%
Transient w/ Power Conversion System: 12.9%
Loss of SWS: 2.1%
Transient w/o Power Main SteanVFW line break: 3.2%
Converslon System: 1.2%
ATWS: 3.1%
lop /Seo: $7,7%
TRANSIENTS WITH POWER TRANSIENTS WITHOUT SPECIAL INITIATORS CONVERSION SYSTEM POWER CONVERSION INCLUDE:
INCLUDE:
SYSTEM INCLUDE:
Loss of Main FW/ Condensate Turbine or Reactor Trip Systems Loss of a DC Bus Pressurizer Control Failures Loss of Circulating Water inadvertent Safety injection System Loss of Control Air System Loss of RCS Flow Loss of Condenser inadvertent MSIV Closure Chart represents distribution of events which may lead to core damage e
Numbers include probability of failure of mitigating equipment or systems e
Loss of SW requires no other failure to cause core damage, but probability of e
occurrence is very low Transients without PCS are less likely than those with PCS, but are equally likely e
to cause core damage It o
j SALEM GENERATING STATION CORE DAMAGE AWARENESS SALEM CORE DAMAGE FREQUENCY INCREASE WHEN A COMPONENT, TRAIN, OR SELECTED SYSTEM IS UNAVAILABLE
\\
{
1000.0 -
E 100.0
!2.
o !!
2 10.0 -
3 1.0 -
MK
^
g g
g g
jg
{
k I
2 8
v i
dt E
g
? i i
~
a'
}!
5 1
Unavailable Component, Train or System The Bar Graph Indicates the relative risk Impact of removal of the identified equipment or combinations of equipment, based on being unavailable for the same time period. For example, removing a 4 Kv Vital Bus increases risk by a factor of approximately 800 times greater than the removal of an Si train over the same period. Individual contributions shown en the Bar Graph are not additive.
OPERATOR ACTIONS MOST IMPORTANT IN PREVENTING CORE DAMAGE 1.
Transfer from ECCS injection to recirculation 2.
Provide altcmate ventilation following a loss of Control Area Air Conditioning or of Switchgear Room Ventilation 3.
Isolation of non-essential CCW loads following the loss of 1 CCW pump 4.
Initiation of rapid boration following an ATWS 5.
Remote shutdown following the loss of the control room 6.
Recovery of a SWS bay which was out for Maintenance 7.
Provide Diesel Generator area ventilaflon by opening hatch after a loss of ventilation 8.
Initiation of feed and bleed when needed 9.
Manual turbine trip following an ATWS 10.
Utillzation of condensate to steam generator following a loss of AFS FOR PRA-RELATED QUESTIONS, CALL EXTENSION 5342 w
1 SALEM GENERATING ST.ATION CORE DAMAGE AWARENESS EVENTS LEADING TO CORE DAMAGE i
l f
Specialinitialors l
LoCA/soTR:19.3%
(except sWSh 0.8%
,ransient w/ Power l
Converion system: 12.9%
{
Loss of SWS: 2.7%
Transient w/o Power Main Stearn/FW Iine break: 3.2%
conversion system: 1.2%
f ATWS: 3.1%
l l
1 l
Lop /sso: 57.7%
(
I i
l l
TRANSIENTS WITH POWER TRANSIENTS WITHOUT SPECIAL INITIATORS I
CONVERSION SYSTEM POWER CONVERSION INCLUDE:
INCLUDE:
SYSTEM INCLUDE:
l Loss of Main FW/Condensata Turbine or Reactor Trip Systems Loss of a DC Bus Pressurizer Control Failures Loss of Circulating Water i
Inadvertent Safety injection System Loss of Control Air System 1
i Loss of RCS Flow Loss of Condenser Inadvertent MSIV Closure 1
{
Chart represents distribution of events Which may lead to core damage l
Numbers include probability of failure of mitigating equipment or systems Loss of SW requires no other failure to cause core damage, but probability of occurrence is very low 1
1 Transients without PCS are less likely than those with PCS, but are equally likely i
j to cause core damage
.I i
Y N-
e SALEM GENERATING STATION CORE DAMAGE AWARENESS SALEM CORE DAMAGE FREQUENCY INCREASE WHEN A COMPONENT, TRAIN, OR SELECTED SYSTEM IS UNAVAILABLE h
1000.0 -
i E
u.
g 100.0 -
gti i
3 8 e.
10.0 -
1.0
- EEE "-
1 I
J J
I' l
[
l y
[
j
[
[I1l$l l
g[
- j
- g. !o 3
l t
q
~
1 c
- E a
Unavailable Component, Train or 6ystem l
4 1
4 The Bar Graph Indicates the relative risk impact of removal of the identifled equipment or combinations of equipment.
3 1
based on being unavailable for the same time period. For example, removing a 4 Kv Vital Bus increases risk by a fact.or ci approximately 800 times greater than the, removal of an Si train over the same period. Individual contributions shown on the Bar Graph are not additive.
OPERATOR ACTIONS MOST IMPORTANT IN PREVENTING CORE DAMAGE 1
1.
Transfer from ECCS injection to recirculation 2.
Provide attemate ventilation following a loss of Control Area Air Conditioning or of Switchgear Room Ventilation 3.
Isolation of non-essential CCW loads following the loss of 1 CCW pump 4
4.
Initiation of rapid boration following an ATWS l
5.
Remote shutdown following the loss of the control room 6.
Recovery of a SWS bay which was out for Maintenance 7.
Provide Diesel Generator area ventilation by opening hatch after a loss of ventilation i
8.
Initiation of feed and bleed when needed g.
Manual turbine trip following an ATWS 10.
Utilization of condensate to steam generator following a loss of AFS FOR PRA-REl.ATED QUESTIONS, CALL EXTENSION 5342
l
\\
l-O PSEG l
Pubbe Senoce Electnc and Gas Cornpany P.O. Box 236 Hancocks Bndge. New Jersey 08038 l
l Hope Creek Generating Station l
l HCT-94-219 TO:
All Nuclear Depanment Procedure Manual Copyholders
)
All Depanment R/C Managers FROM:
W. H. Schell, NAP Project Manager Technical Staff Engineer - Hope Creek m
SUBJECT:
ADDENDUM TO NC.NA-AP.ZZ-0020(Q)
ELECTRONIC PROCESSING OF DEFICIENCY REPORTS (DRs) l USING THE MMIS CORRECTIVE ACTION DATA BASE (CADB)
DATE:
August 26,1994 Effective immediately, the new Corrective Action Data Base (CADB) should be used in lieu of Form NC.NA-AP.ZZ-0020-1, Deficiency Report, to document discovery, review, l
prioritization, evaluation, resolution and closure of Ddiciency Repons (DRs).
Guidelines, basic commands and requirements for initiating a Problem Report (PR) and using the CADB for DRs are included as an attachment to this memorandum. Additional guidelines covering general use of the CADB can be found in NAP-58 or tim memorandum attached to NAP-58.
This memorandum provides interim control and direction for use of the new CADB for DR processing until NC.NA-AP.ZZ-0020(Q), Control of Nonconforming Components and Structures (NAP-20), Rev. 3 is issued. It should be placed at the front of NAP-20, between the Cover Page and Page 1 of the procedure. Other than minor adjustments to accommodate electronic processing via the new CADB, the basic process (including definitions and responsibilities) described in NAP-20 will not change as a result of CADB implementation.
I Currently, electionic processing of DRs is the preferred alternative to paper processing.
A'ter an initial implementation period of 30 days, use of the CADB for processing DRs will J
be mandatory and paper processing should only be performed if the computer data base is unavailable, l
Any questions or feedback should be directed to Hal Lowe, QA - Programs and Audits at l
extension 1208, Bill Schell, Hope Creek Technical at extension 3495, or Brian Connor, Salem Technical at extension 2025.
WHS/SEG Attachments: Attachment 1, Guidelines for Processing Deficiency Repons
(
ihe Energy Peep;e ss.u n usuou+
1 ATTACHMENT 1 GUIDELINES FOR PROCESSING DEFICIENCY REPORTS Page 1 of 5 1.0 Problem Report Initiation 1.1 To create a Problem Report from a Work Order, at a " Work Order Activity" screen, type "CRPR" on the command line and press ENTER. Proceed to Step 1.5.
1.2
'Ihe Conective Action Data Base (CADB) is accee=~i by choosing option "Q" from the Main Menu screen of MMIS.
1.3 From the Corrective Action screen, Select Option "1", PROBLEM REPORT PROCESSING and Mode "2", CREATE NEW DATA at the secondary Options j
Menu. Press ENTER.
1.4
'Ihe next screen will prompt the user for the PR TYPE. The system shows the default setting of "PR".
This code is to be used during the initiation stage for all Problem Reports, including DRs. This screen will also allow the user to copy an existing Problem Report by entering the number on the indicated line. ' Itis line is to be left blank when creating a new PR. Press ENTER.
1.5
'Ihe " Problem Report Description" screen is Imw displayed. Press ENTER on the cornmanni line to highlight the fields which require entries to be made. All other j
fields are not required, but available information should be entered as applicable.
Use the Fil key to identify the accymble codes in any field.
1.6 If drawings or other documents are required in order to adequately describe the problem, the field " Attachment?" is to be. marked "Y" and a cover page should be generated by pressing
- PRINT SCREEN" to route with the attachments.
1.7 When all required fields are completed and any other applicable infonnation has been entered, press ENTER.
)
1.8 The " Problem Report Tracking / Trending" screen will be displayed. Enter the
" Detection Code" and any other codes that may be known. Press ENTER.
4 1.9 If tie same person will continue processing the Problem Report, proceed to Step 2.5.
1.10 If processing is complete, use the F4 key to back out of the Problem Report. This must be done to save the data and allow processing of the PR to continue.
2.0 Problem Report Review 2.1
'Ihe identified PR should be reviewed for accuracy. ' Ibis may be done by the initiator, the initiator's supervisot, or other designated individual.
l
7 ATTACHMENT 1 GUIDELINES FOR PROCESSING DEFICIENCY REPORTS Page 2 of 5 2.2 From the Corrective Action screen, Select Option "1", PROBLEM REPORT f
PROCESSING and Mode "1", SEARCH EXISTING DATA at the secondary Options j
j Menu. Press ENTER.
t j
2.3 Using the options available on the Problem Repon Search Options screen, sealth for j
the desired Pmblem Report.
t j
2.4 At the " Problem Report Description" screen, press F6 to enter the " change" mode.
The fields which may be changed will be highlighted.
2.5 Indicate the " Responsible Dept" for the PR.
q 2.6 When all required entries have been made, type REVIEW on the command line and l
press ENTER. This will change the PR status to REVWD. 'Ihis step electronically captures the signature of the reviewer on the PR.
i 1
2.7 If the same person will continue processing the Problem Report, proceed to Step 3.3.
2.8 If processing is complete, use the F4 key to back out of the Pmblem Report. This
+
m ist be done to save the data and allow processing of the PR to continue.
3.0 Deficiancy Report Initiation NOTE i
i i
l At any point during the processing of a DR, the " PRINT" command may be i
entered on the command line to create a paper copy of the DR.
(
3.1 In order to initiate a DR, the Problem Report must be in the REVWD status and the person initiating the DR must have the required security access.
i 3.2 At the "Pmblem Report Description" screen, press F6 to enter the " change" mode.
l The fields which may be changed will be highlighted, i
j 3.3 At the " Problem Report Description" screen, type "CRDR" on the command line and j
press ENTER. ' Ibis will create a DR. Any required fields that have not been previously filled in will be highlighted. An entry in these fields is required prior to continuing.
3.4
'Ibe system will place an "X" next to the DR block on the " Problem Report Description" screen and will create an evaluation for the SNSS to review the PR.
The evaluation will indicate EVAL TYPE = DRSS.
3.5 Use the F4 key to back out of the Problem Report. This must be done to save the data and allow processing of the PR to continue.
ATTACHMENT 1 GUIDELINES FOR PROCESSING DEFICIENCY REPORTS l
Page 3 of 5 3.6 De SNSS/NSS should access the Problem Report and perform the following:
3.6.1 At the " Problem Report Description" screen, press F6 to enter the " change" mode.
De fields which may be changed will be highlighted.
3.6.2 Review the PR for operability concerns and access the Eval with the EVAL TYPE = DRSS by typing EVAL or P3 on the command line. Use the F7 and F8 i
l keys to scroll through the evaluations. Press ENTER on the command line to j
l highlight the fields which require entries to be made. Enter all required information
)
l and any other applicable information. If an Action Statement number i.e entered in the i
A/S NUM field, the current time and date will automatically be entered in the A/S DATE-TIME field unless manually entered. If ECG is "Y", then identify the ECG Step number in the Remarks / Comments section on Page 4.
3.6.3 If there is an Action Statement, the Eval should be placed in the disposition status by typing " DISP" on the command line. If there is no Action Statement, type
" COMPLETE" on the command line.
3.6.4 De system will create an evaluation for the Technical Engineer to review the PR.
i De evaluation will indicate EVAL TYPE = DRSE. Use the F4 key to back out of the Problem Report. His must be done to save the data and allow processing of the i
PR to continue.
3.7 De Technical Engineer should access the Problem Report and perform the following:
3.7.1 At the " Problem Report Description" screen, press F6 to enter the " change" mode.
The fields which may be changed will be highlighted.
3.7.2 Access the Eval wim the EVAL TYPE = DRSE, by typing EVAL or P3 on the command line. Use the F7 and F8 keys to scroll through the evaluations.
3.7.3 Enter the name of the System Engineer assigned to disposition the DR.
3.8 De System Engineer should access the Problem Report and perform the following:
3.8.1 Review the PR to verify for DR and access the Eval with the EVAL TYPE = DRSE, by typing EVAL or P3 on the command line. Use the F7 and F8 keys to scroll through the evaluations. Press ENTER on the c===d line to highlight the fields which require entries to te made.
3.8.2 If the DR is not valid, at the " Problem Report Description" screen, type "ERDR" on the command line. He system will remove the "X" from the DR block on the
" Problem Report Description" screen. Access the DRSE Eval, type " COMPLETE" i
l on the command line, and inform the initiator.
A'ITACHMENT 1 GUIDELINES FOR PROCESSING DEFICIENCY. REPORTS i
Page 4 of 5 i
3.8.3 If the DR is valid but will not be immediately dispositioned, type " START" on the command line to place the DRSE Eval in the WIP status, i
i 3.8.4 Perform evaluation / disposition and enter all required infonnation and any additional information. Type " DISP" on the command line and forward any attachments to QA.
l 3.9 QA should review the DRSE Eval and type " REVIEW 2" on the command line and forward the package to the ANI. If an ANI review is not required, QA should type 4
I
" COMPLETE" on the command line.
i 3.10 If an ANI review is required, the ANI should review the DRSE Eval and type
" COMPLETE" on the command line.
a 3.11 When the DRSE Eval is COMPLT, then the DR is ready to work. The system will create an evaluation for the Maintenance Supervisor to review the PR. The j
evaluation will indicate EVAL TYPE = DRSC.
l j
3.12 To print the DR, go to the DRSE Eval, press F6 to enter the change mode and type
" PRINT" on the command line. Indicate the DR and printer ID on the screca.-
3.13 'Ihe Maintenance Supervisor should access the Eval with the EVAL TYPE = DRSC and implement any identified corrective action. When work is started, type " START" on the command line to change the Eval status to "WIP".
l 4.0 Deficiancy Paanrt Revician l
4.1 If it becomes necessary to revise a DR, the System Engineer should perfonn the
)
following:
i j
4.1.1 At the " Problem Report Description" screen or the " Evaluation" screen, type "CREVAL" on the command line and press ENTER. This will create a blank Eval, 4.1.2 Press ENTER to highlight the required entries. At the " EVAL TYPE" field, type "DRSE" to create a new DRSE Eval. Complete the r==ialag required sections, then press ENTER. 'Ihis will change the Eval status to ASSGND (Assigned).
4.1.3 The new DRSE may be for an addendum change only, or to supercede the original DRSE. Make a note on the " Remarks / Comments" page of the original DRSE
]
referring to the revision.
4.2 Completion of the new DRSE will not auto-generate a DRSC. The original DRSC should be used to capture the close out signatures.
4 i
a
o A'ITACHMENT 1 GUIDEI.INES FOR PROCESSING DEFICIENCY REPORTS Page 5 of 5 5.0 Deficiency Report Closure 5.1 Upon completion of the corrective action, the Maintenance Supervisor should disposition the DRSC Eval by typing " DISP" on the command line and forwani any attachments to QA.
5.2 QA should review the DR for closure and type " REVIEW 2" on the command line of the DRSC Eval and forward the package to the ANI. If an ANI review is not required, QA should type " COMPLETE" on the command line.
5.3 If an ANI review is required, the ANI should review the closure and type
" COMPLETE" on the command line on the DRSC Eval.
5.4 If there is an Action Statement and the DRSS Eval is still open, the Maintenance Supervisor should notify the SNSS/NSS that the corrective action is complete. The SNSS/NSS should access the DRSS Eval and type " COMPLETE" to close the eval when the Action Statement is exited.
5.5 When all Evals associated with the resolution are statused as COMPLT, the implementing department may close the DR by typing " APPROVE" or "CLOSE" on the command line at the " Problem Report Description" screen.
9 4
1.
. ~ -.
h
' ~4 Page 1 of 3
'PSE&G NUCLEAR DEPARTMENT NC.NA-AP.ZZ-0020(Q) - REV. 2 l
CONTROL OF NONCONFORMING COMPONENTS AND STRUCTURES SalemTechnicalDepartment/
SPON8OR ORGANIZATION:
l CONTROL COPY p REVTSTON
SUMMARY
I 9 ()
l' i
l This general revision:
)
{
.J 1.
Changes the title of the procedure.
l 2.
Contains editorial changes to the text.
3.
Deletes the phrase "AI.T. TYPES OF ASME NONCONFORMTNG CODE TTEMS".
4.
Deletes Attachment 1, Deficiency Report Flowchart.
l l
5.
Redefines the procedure's purpose to address physical defects that cannot be restored to an acceptable condition by " routine l'
maintenance activities" (Section 1.0).
l 6.
Repl aces the ters
" rework process" with " routine maintenance activi ti es" (Section 1.0).
NNJ CONCUR:
General Manager - Quality Assurance /
'Date Nuclear Safety Review APPROVED:
M b
/Vice President - Nuclear Engineering
/ Ddte 8PbO bdW%InrA.
M3 APPROVED:
A GRneral Man'ager - Nuclear Services Mat'e
/
fI l
APPROVED:
-W-MU General r-H e
Operations
' Date APPROVED:
o //W M
f 7
Ger(hifal Manage'r - Salen Operations Date i
?Y
b.
~
Page 2 of 3 NC.NA-AP.55-0020(Q) - REY. 2 CONTROL OF NONCONFORMING COMPONENTS AND STRUCTURES REVISION
SUMMARY
(Continued) 7.
Deletes the requirement to initiate DRs for nonconforming Code items greater than la in diameter which are " replace-in-kind" l
(for example, bolting replacement, bonnet replacement, etc.)
j (Section 2.0).
l 8.
Removes ASME Class 1 and 2 piping components from consideration and limits the use of the procedure to ASME Class 3 piping components (NRC Generic Letter 90-05) (Section 5.1.4).
9.
Adds the requirement to initiate DRs for the replacement-in-i kind of ALL nonconforming nuclear Code items 1" or less nominal pipe size, specifically, piping, pumps, valves and their supports (Section 5.1.5).
l 10.
Requires the DR Action Complete section be completed before a restored component or structure is to be considered operable when Technical Specification Limiting condition of Operation l
(LCO) Action Statements are involved (Section 5.1.6).
l 11.
Adds the requirement for the System Engineer to attach the 10CFR50.59 Review and Safety Evaluation to the DR (Section i
5.3.1.f.).
12.
Adds the requirement to make the Non-DR part of the work package (Section 5.3.2.a.).
l 13.
Changes the requirement for coordinating the SQA review of the i
dispositioned DR from the System Engineer to the Job i
i Supervisor / Supervisor / Planner (Section 5.3.2.b.).
14.
Clarifies Planner / Job Supervisor responsibilities for
]
(
Use-As-Is dispositions (Section 5.5.1,b.3. and 5.5.2.b.3.).
15.
Deletes the requirement for the Job Supervisor to enter the cause code on the DR (Section 5.5.2).
J i
(
16.
Revises the method by which Station Quality Assurance can verify the completion of the restoration activity (section 5.6.1).
l 17.
Adds the requirement for the Job supervisor to present the completed DR to the SNSS/NSS when LCOs have been entered (Section 5.6.3.b.2).
l m,
=,
i.
6' Page 3 of 3 NC.NA-AP.ZZ-0020(Q) - REV. 2 CONTROL OF NONCONFORMING COMPONENTS AND STRUCTURES REVISION
SUMMARY
(Continued) 18.
Changes the responsibility for making copies of the completed DR from SQA to the Job Supervisor (Section 5.6.3.c.).
19.
Adds the requirement for the SNSS/NSS to review completed DRs when LCOs have been entered (Section 5.6.4 and Form NC.NA-AP.ZZ-0020-2 (Action Complete section)).
20.
Adds provisions for revising DRs (Section 5.7).
21.
Adds provisions for cancelling DRs (Section 5.8).
22.
Clarifles NPRDS reporting (Section 5.9).
j i
23.
Contnins minor revisions to the Deficiency Report (Form NC.NA-AP.ZZ-0020-1).
24.
Adds additional columns to the Deficiency Report Log (Form NC.NA-AP.ZZ-0020-2).
Major changes have been identified with revision bars.
This revision meets the biennial review requirements specified in NC.NA-AP.ZZ-0032(Q).
IMPLEMENTATION REQUIREMENTS This procedure revision is effective upon issue.
DRs initiated prior to the issuance of this revision shall be processed to completion per Revision 1 of the procedure.
i a
~.
i NC. NA-AP. Z Z-0 02 0 ( Q)
CONTROL OF NONCONFORNING CONPONENTS AND STRUCTURES TABLE OF CONTENTS Section Title Page 1.0 PURPOSE............................................... 2 2.0 SCOPE................................................. 2 i
3.0 RESPONSIBILITIES 2
4.0 PROCESS DESCRIPTION................................... 5 5.0 PROCEDURE............................................
5 5.1 General Guidelines.............................
5 5.2 Identifying Nonconforming Components / Structures 6
5.3 Dispositioning Deficiency Reports..............
7 i
5.4 Reviewing Deficiency Reports...................
9 5.5 Implementing Deficiency Reports.................
9 5.6 Reviewing Completed Deficiency Reports......... 11 I
5.7 Revising Deficiency Reports.....................
12 I
5.8 Cancelling Deficiency Reports.................. 13 5.9 Reports........................................ 14 5.10 Records........................................ 14 a
6.0 DEFINITIONS 14
7.0 REFERENCES
........................................... 15 ATTACHMENTS N/A EXHIBITS N/A FORMS NC.NA-AP.ZZ-0020 Deficiency Report Rev. 2 NC.NA-AP.ZZ-0020 Deficiency Report Log Rev. 2 Nuclear common Page 1 of 16 Rev. 2
N,
- E NC.NA-AP.ZZ-0020(Q)
CONTROL OF NONCONFORMING COMPONENTS AND STRUCTURES l
1.0 PURPOSE 1.1 To describe the program for controlling components and CD-1788 structures (C/S) exhibiting defects which cannot be restored to an acceptable condition by " routine maintenance activities".
1.2 The term " nonconforming C/S" shall refer to those C/Ss that have been determined to be unable to be restored to an acceptable condition by " routine maintenance activities".
2.0 SCOPE 2.1 The program shall be used for restoring nonconforming category Q, Qs, Qsh, F,
and R C/Ss (Hope Creek), safety related C/Ss (Salem), and American Society of Mechanical Engineers (ASME) vessels.
The categories are identified in the Managed Maintenance Information System (MMIS)).
2.2 The program should be used for restoring nonconforming significant balance of plant C/Ss.
The program may be used for restoration of other nonconforming balance of plant C/Ss at the discretion of the Technical Departments.
3.0 RESPONSIBILITIES 3.1 Technical Department Manaaerg are responsible for implementation of the program.
3.2 gpb supervisors. Supervisors and Planners are responsible for:
o Initiating Deficiency Reports ((DRs), Form NC.NA-AP.ZZ-0020-1) to identify nonconforming C/Ss o
contacting the responsible Technical Department System Engineer for assistance in determining whether the restoration activity meets the definition of " routine maintenance activities".
3.3 senior Nuclear Shift Supervisors /Muclear Shift supervisors (8NSS/ MSS) are responsible for reviewing DRs for Technical Specification operability considerations.
Nuclear Common Page 2 of 16 Rev. 2
NC.NA-AP. 22-0 02 0 (Q) i 3.4 Technical'Denartment System Enaineers (System Engineers) are responsible for:
)
i CD-915A o
Preparing DR dispositions to restore l
nonconforming C/Ss to an acceptable condition 3
o Preparing 10CFR50.59 Reviews and Safety Evaluations per NC.NA-AP.ZZ-0059(Q), 10CFR50.59 Reviews and Safety Evaluations, as applicable, to support DR dispositions i
o Ensuring DRs and 10CFR50.59 Reviews and Safety d
Evaluations for which 10CFR50.59 applies are presented to the Station operations Review i
Committee (SORC) prior to implementation of the Disposition o
Coordinating the reporting of nonconforming C/Ss
{
which meet 10CFR21 reporting requirements with the Station Licensing Engineer and Station Quality Assurance i
j o
coordinating recommended Equipment Qualification and Appendix R program changes resulting from 5
nonconforming C/S investigations
)
o Evaluating nonconforming C/Ss for potential generic issues CD-915A o
Considering the impact of a failed C/S on any j
other C/S in parallel or series with it o
Contacting the cognizant Engineering & Plant y
Betterment representative to resolve
'9nfiguration control issues resulting from j
dispositioning DRs.
1 j
3.5 Technical Denartment Technical Staffs (Technical i
Staff) are responsible for' 1
o Maintaining DR status.
Form NC.NA-AP.ZZ-0020-2, l
j Deficiency Report Log, contains the minimum required information.
1 I
o Transmitting copies of DRs and Safety Evaluations for which 10CFR50.59 applies to the Manager -
Nuclear Safety Review o
Maintaining copies of DRs until the DR Action Complete sections are complete.
3
\\
I Muclear common Page 3 of 16 Rev. 2 2
1 w-+
w.
l l
~
NC.NA-AP.ZZ-0020(Q) 3.6 Station operations Review Committees are responsible for reviewing DRs and Safety Evaluations for which 10CFR50.59 applies prior to implementation of the disposition to determine the accuracy and applicability of Unreviewed Safety Question (USQ) determinations.
3.7 Maintenance Department NPRDS Coordinators are responsible for reviewing'DRs and ensuring Nuclear Plant Reliability Data System (NPRDS) reportability requirements are met.
J 3.8 The Manaaers - Station cuality Assurance (801) are j
responsible for reviewing DRs per the Operational l
Quality Assurance Program, 3.9 Enaineerina and Plant Betterment (EEPB) represent-atives are responsible for:
i l
o Assisting in dispositioning DRs, as requested o
Updating the Configuration Control Program as required.
3.10 The Manaaer - Nuclear Safety Review is responsible for:
I o
Performing independent reviews of DRs and Safety Evaluations for which 107FR50.59 applies to verify the accuracy and applicability of USQ determinations NOTE l
These reviews are independent of the 80RC function and need not be completed prior to implementation of the dispositions.
l o
Transmitting review results to the cognizant Technical Department f.anager o
Reporting review results to the Vice-President and Chief Nuclear Officer per the Technical Sp6cifications.
3.11 The Authorised Nuclear Inservice Insnector (ANII) l is responsible for reviewing DRs written for noncon-forming American Society of Mechanical Engineers (ASME)
Code items to verify compliance, in part, with the Nuclear Department Repair Program Manual.
4 Nuclear Common Page 4 of 16 Rev. 2
NC.NA-AP.23-0020(Q) 4.0 PROCESS DESCRIPTION 4.1 Defects affecting C/Ss will normally be identified /
corrected by " routine maintenance activities" per NC.NA-AP.ZZ-0009(Q), Work Control Process.
DRs will be used for the restoration of defects when " routine maintenance activities" cannot be used.
1 4.2 DRs will also be used to accept nonconforming C/Ss for l
continued use when corrective actions are not required.
This may include the use of DRs to document acceptance of procedural out of tolerance conditions.
4.3 10CFR50.59 Reviews and Safety Evaluations will be prepared for nonconforming Q, Qs, Qsh, F,
and R (Hope Creek) and safety related (Salem) C/Ss dispositioned as REPAIR or USE-AS-IS.
4.4 DRs and 10CFR50.59 Safety Evaluations for which 10CFR50.59 applies will be approved by SORC prior to returning the nonconforming C/S to an operable status, as applicable.
4.5 Copies of DRs and 10CFR50.59 Safety Evaluations for which 10CFR50.59 applies will be sent to the Manager -
Nuclear Safety Review.
5.0 PROCEDURE 5.1 General Guidelines 5.1.1 Nonconforming components removed for restoration shall be identified with an Equipment Malfunction Information System (EMIS) tag per NC.NA-AP.ZZ-0009(Q) if they will not be returned to their original installed location.
5.1.2 Nonconforming components retained for investigation, maintenance, or salvage shall be identified with an EMIS tag, segregated from acceptable components, where practical, and stored in an manner which prevents further degradation of the components.
5.1.3 Nonconforming components which are not going to be restored to an acceptable condition shall be identified as such, segregated from acceptable components, where practical, and disposed of in a timely manner.
5.1.4 Nonconforming ASME Class 3 piping components which can-CD-843F not be restored to an acceptable condition by standard Costa repair or replacement may have temporary reversible leak limiting measures performed, provided that Nuclear Regulatory Commission (NRC) Generic Letter 90-05 is Nuclear Common Page 5 of 15 Rev. 2
)
l NC.NA-AP.ZZ-0020(Q) i followed.
The responsible System Engineer shall be j
contacted to coordinate the required inspections, etc.
5.1.5 DRs shall be used to document the replacement-in-kind of &LL nonconforming nuclear Code items (" Code" l
refers to ASME items 1" or less nominal pipe size (NPS), specifically, piping, pumps, valves and their j
supports).
5.1.6 C/Ss exnibiting defects which result in Technical Specification Limiting Condition for Operation (LCO)
Action Statement entries SEALL NOT BE CONSIDERED OPERABLE until the DR Action Complete section is signed off.
5.1.7 Design changes or temporary modifications prepared to restore nonconforming C/Ss shall reference the applicable DR by number and stipulate that they cannot be revised / cancelled without the concurrence of the responsible System Engineer, SQA, and ANII, if applicable.
If the design change or temporary modification is cancelled, the DR shall be revised to identify the reason for the cancellation and re-dispositioned per Section 5.3.
5.1.8 Work Orders (WO, NC.NA-AP.ZZ-0009(Q)) prepared for future restoration activities involving REPAIR, USE-AS-IS or REPLACEMENT (1" or less NPS NUC. CODE ITEM) dispositions shall reference the applicable DR by number and stipulate that they cannot be revised /
cancelled without the concurrence of the responsible System Engineer, SQA, and ANII, if applicable.
5.1.9 Post-Maintenance Testing and Operability Retests (NC.NA-AP.ZZ-0050(Q), Station Testing Program) for nonconforming C/Ss should be identified on the Work Request /WO ([WR), NC.NA-AP.ZZ-0009(Q)) and NOT ON THE ER.
5.1.10 WOs in the Managed Maintenance Information System (MMIS) that reference DRs shall not be updated as " work complete" until both the completed DR and associated work package have been given to the Planning group.
5.2 Identifyina Nonconformina Connonents/ Structures 5.2.1 Individuals identifying defects, etc. affecting C/Ss l
CD-55SD shall inform their Supervisor of the condition.
1
)
t Nuclear Common Page 6 of 16 Rev. 2 1
1 1
- '=
NC. NA-AP. Z Z-0 02 0 (Q) 5.2.2 Supervisors (Job Supervisors, Planners, etc.)
investigating the condition shall:
When a DR is not required, advise the identifying a.
person of the method to be used to correct the j
l condition.
1 l
b.
Ensure a WR/WO is initiated to investigate the I
condition if only a symptom of the problem is known (for example, valve leaks through, etc.).
c.
If routine maintenance activities cannot be used to restore the C/S to an acceptable condition, l
initiate a DR.
d.
Complete the DR Description section and enter the department designator and year (for example, HMD or SMD-93-) and sign /date the DR.
e.
Present the DR to the SNSS/NSS.
1 5.2.3 The Senior Nuclear Shift Supervisor / Nuclear Shift Supervisor shall:
CD-525E a.
Review the DR description section to determine C/S operability per the Technical Specifications.
1.
If operability IS NOT affected, enter j
N/A for the LCO number, date, and time in j
the DR Description section or, i
2.
If operability Ig adversely affected, enter LCO nin=her and arciration date and time in the DR Description section.
b.
Sign /date the DR Description section and return the DR to the Initiator.
5.2.4 The Initiator shall present the DR to the responsible System Engineer.
l 5.3 Disnositionina Deficiency Reports 5.3.1 The System Engineer shall:
a.
Review the description of the nonconforming C/S.
1 b.
If a DR IS_NOT warranted:
1.
Check Non-DR, enter the basis for the l
determination in the DR Disposition section and sign /date the Disposition section.
I i
Nuclear Common Page 7 of 16 Rev. 2
NC.NA-AP.ZZ-0020(Q) 2.
Notify the SNSS/NSS that the C/S is not nonconforming per this procedure.
3.
Return the Non-DR to the Initiator.
c.
If a DR It warranted, review the Deficiency Report Log and enter the next sequential number on the DR and Deficiency Report Log.
d.
Complete the DR Disposition section.
Design changes (NC.NA-AP.ZZ-0008(Q), Control of Design and Configuration Change, Test, and Experiments),
and temporary modifications (NC.NA-AP.ZZ-0013(Q),
control of Temporary Modifications) may be used to restore nonconforming C/Ss, as required.
Contact the cognizant EGPB representative if assistance is required.
For a USE-AS-IS disposition, enter "No Action Required" in the DR Disposition and Action Complete sections.
I e.
Sign /date the DR Disposition section.
In l
sddition, for a USE-AS-IS disposition, sign /date beneath the "No Action Required" entry in the DR Action Complete section.
f.
Prepare a 10CFR50.59 Review and Safety Evaluation for a REPAIR or USE-AS-IS disposition and attach l
it to the DR.
l g.
If 10CFR50.59 applies, present the DR and l
10CFR50.59 Safety Evaluation to SORC.
1 h.
Attach all related disposition documentation to the DR or reference its location on the DR (for example, see Wo, Code Job Package ([CJP),
NC.NA-AP.ZZ-0028(Q), etc.).
When additional pages are required, enter the DR number in the upper right hand corner of each page.
i.
Copy the DR and 10CFR50.59 Safety Evaluation and give the copies to the Technical Staff.
j.
Return the original DR to the Initiator.
5.3.2 The Initiator shall:
a.
Place the Non-DR in the applicable work package.
b.
Coordinate SQA review of the DR.
Nuclear common Page 8 of 16 Rev. 2 i
NC.NA-AP.ZZ-0020(Q) 5.3.3 The Technical Staff shall.
a.
Update the Deficiency Report Log, as applicable.
b.
When 10CFR50.59 applies, copy the DR and 10CFR50.59 Safety Evaluation and transmit to the Manager - Nuclear Safety Review, c.
File the copy of the DR and 10CFR50.59 Safety Evaluation in the Technical Department DR file.
5.4 Reviewina Deficiency Reports 5.4.1 Station Quality Assurance shall:
a.
Review the DR Disposition section.
Resolve dis-position concerns with the responsible System j
Engineer.
If agreement cannot be reached, contact the responsible Technical Engineer to resolve the concerns.
i b.
When acceptable, sign /date the DR Review section.
In addition, for a USE-AS-IS i
disposition, sign /date the DR Action Complete section.
c.
Coordinate ANII review of the Disposition, if applicable.
When not applicable, enter N/A and initial /date the section.
Coordinate ANII Disposition concerns with the responsible System Engineer.
d.
Return the DR to the Initiator.
5.4.2 The Authorized Nuclear Inservice Inspector will review dispositions for Code items and, if acceptable, sign /date the DR Review section and return the DR to the SQA representative.
5.5 Tanlementina Deficiency Reports 5.5.1 The Planner shall:
Resolve disposition concerns with the responsible a.
System Engineer.
If agreement cannot be reached, contact the responsible Technical Engineer to resolve the concerns.
b.
Verify that the DR Disposition and Review l
sections have been signed.
For a USE-AS-IS disposition:
~
1 j
Nuclear Common Page 9 of 16 Rev. 2
(
NC.NA-AP.22-0020(Q) i 1.
Verify that the System Engineer /SQA have signed / dated the DR Action Complete section.
2.
Sign /date the DR Action Complete section on the Job Supervisor's line.
3.
If C/S operability was affected, (LCO number / expiration date/ time entered by the SNSS/NSS), coordinate SNSS/NSS review of the DR.
When not applicable, enter N/A and initial /date the section.
4.
Place the DR with the applicable work package.
c.
If restoration is required, place the DR in the applicable work package and forward it to the responsible Job Supervisor or place it in the work pending file.
5.5.2 The Job Supervisor shall:
a.
Resolve DR disposition concerns with the responsible System Engineer.
If agreement cannot be reached, contact the responsible Technical Engineer to resolve the concerns.
b.
Verify that the DR Disposition and Review l
sections have been signed.
For a USE-AS-IS disposition:
1.
Verify that the System Engineer /SQA have signed / dated the DR Action Complete section.
2.
Sign /date the DR Action. Complete section.
3.
If C/S operability was affect.ed, (LCO nunner/ expiration date/ time er:tered by the SNSS/NSS), coordinate SNSS/NSS review of the DR.
When not applicable, enter N/A and initial /date the section.
4.
Place the DR with the applicable work package.
{
c.
If restoration is required, ensure the work is performed as stated in the DR Disposition section 1
and applicable work package, d.
EMSURE TBE DR MUMBER EAS BERM ENTERED ON TEE WR/Wo.
t l
Nuclear common Page 10 of 16 Rev. 2
]
l
NC.NA-AP.22-0020(Q) e.
Sign /date the DR Action Complete section.
f.
Coordinate SQA review of the DR.
l 5.6 Reviewina connlated Deficiency Renorts 5.6.1 Station Quality Assurance shall:
a.
Verify the work was performed by:
1 1.
Witnessing the performance of the work or, l
2.
Reviewing the work package documentation.
l b.
If the work is unacceptable, identify the l
condition and return the DR to the Job Supervisor.
l l
l c.
When the work is acceptable, sign /date the DR Action Complete section.
d.
Coordinate ANII review of the work performed, if applicable.
Enter N/A and initial /date the 1
l l-section when not applicable.
1 e.
Return the original DR to the responsible Job Supervisor.
5.6.2 The Authorized Nuclear Inservice Inspector will review the work performed for Code items and, if acceptable, sign /date the DR Action Complete section and return the DR to the SQA representative.
5.6.3 The Job Supervisor shall:
a.
Resolve SQA or ANII concerns with the work that was performed.
1 l
b.
If'C/S operability was affected, (LCO number /
expiration date/ time entered by the SNSS/NSS),
l coordinate SNSS/NSS review of the DR.
When not applicable, enter N/A and initial /date the section.
l I
c.
Copy the completed DR and transmit the copy to the Technical Staff.
I d.
Ensure the original DR is placed in the work package and forwarded to the Planning Group.
I l
Nuclear common Page 11 of 16 Rev. 2 l
l NC. NA-AP. 2 2-0 0 2 0 (Q)
- ~~
l 5.6.4 The Senior Nuclear Shift Supervisor / Nuclear Shift Supervisor shall:
a.
Review the completed DR and take the appropriate l
actions to exit the LCO, if applicable.
b.
Sign /date the DR Action Complete section and return the DR to the, Job Supervisor.
5.6.5 The Technical Staff shall:
a.
Update the Deficiency Report Log to indicate that the DR is closed.
l b.
Discard the copy of the DR and 10CFR50.59 Safety Evaluation, if applicable.
5.6.6 Planning Groups shall:
a.
Ensure the original closed DR and 10CFR50.59 Safety Evaluation, if applicable, are included in the work package, b.
Update MMIS to indicate that the DR is closed.
5.7 Revisina Deficiency Reports Revisions to dispositioned DRs shall be processed as i
follows.
5.7.1 The responsible System Engineer shall:
a.
For revisions that DO NOT CEANGE the scope, intent or 10CFR50.59 Safety Evaluation, enter /
l line out and initial /date the DR Disposition ~
f section.
Coordinate SQA review of the revision.
b.
For revisions that CEANGE the scope, intent or 10CFR50.59 Safety Evaluation:
1.
Initiate a revised DR with a
-1,
-2, etc.,
after the number.
Enter "See Rev.
O, 1,
etc." for those sections that do not change.
2.
Process the revised DR per Sections 5.2 through 5.4.
3.
Attach the revised DR to the original DR.
ll
{
l Nuclear Common Page 12 of 16 Rev. 2
___m.
~
NC.NA-AP. 22-0020(Q) 5.7.2 Station Quality Assurance shall:
a.
Review the revision (Section 5.7.1 a.) and if in agreement, initial /date.
b.
Coordinate ANII review of the revision, if applicable. Enter N/A and initial /date the section when not applicable.
5.8 Cancellina DeficiencT Reports DRs may be cancelled when changes in plant status, etc.
render the proposed restoration unwarranted, provided the restoration hAS NOT begun.
l If the restoration has begun, the DR shall be revised l
per Section 5.7 to reflect the cancellation.
5.8.1 The responsible System Engineer shall:
i a.
Enter " CANCELLED" and the reason for cancelling l
in the DR Disposition section.
Sign /date above the existing signature.
1 b.
Coordinate SQA review of the DR.
l c.
Advise the SNSS/NSS the,C/S is not nonconforming per this procedure.
l 5.8.2 Station Quality Assurance shall:
J a.
Review the reason for cancelling and resolve any concerns with the responsible System Engineer.
j If agreement cannot be reached, contact the responsible Technical Engineer to resolve the concerns.
b.
When acceptable, sign /date the DR Review section.
If already reviewed, sign /date above the existing signature.
c.
Coordir, ate ANII review of the revised DR Disposition, if applicable.
Enter N/A and initial /date the section when not applicable.
Coordinate ANII concerns with the responsible System Engineer.
d.
Return the cancelled DR to the responsible Job l
Supervisor / Planner.
i I
l i
Nuclear Common Page 13 of 16 Rev. 2 i
I I
1 NC.NA-AP.ZZ-0020(Q) 5.9 Reports l
1 Maintenance Department NPRDS Coordinators shall review DRs and report applicable nonconforming C/Ss to NPRDS.
l 5.10 Records Planning Groups shall ensure closed / cancelled DRs, 10CFR50.59 Safety Evaluations and Non-DRs are retained per NC.NA-AP.ZZ-00ll(Q), Records Management Program.
I 6.0 DEFINITIONS 6.1 ASME Yassel - All Non-Nuclear Balance of Plant l
power boilers, heating boiler, pressure vessels, boiler l
external / boiler proper piping (defined by PG-58, ASME Section I) and valves which are constructed under ASME l
l rules, and which are jurisdictionally subject to third l
party involvement with an Authorized Inspector.
6.2 Nuclear Code Item - Nuclear Class 1, 2,
3, and metal containment (MC) components and their supports; and core support (CS) components irrespective of the i
l components' original Construction code (for example, ANSI B31.7, ASME Section III, VII).
The term item when I
used with the modifiers " Nuclear Code" shall further be l
understood to denote all items such as piping systems, vessels, piping sub-assembly, pumps, valves, component supports, material, parts, et appurtenance as defined in ASME Section III and ASME Section XI Codes.
See NC.NA-AP.ZZ-0028(Q), Code Job Package, for additional clarification, i
6.3 Repair - Restoring a non Code item to a safe and l
satisfactory operating condition even though it may not conform to original design specifications.
j 6.4 Repair (ASME Vessell - Work necessary to restore an ASME Vessel, as defined by Section 6.1 of this procedure, to a safe and satisfactory operating condition, provided there is no deviation from the original design.
See NC.NA-AP.ZZ-0028(Q), code Job Package, for additional clarification.
6.5 Repair (Nuclear Code item) - Work necessary to I
restore any Nuclear Class 1, 2,
3, MC, or CS item by welding, brazing and metal removal, to a safe and satisfactory operating condition, provided that in all cases the existing design requirements are not modified, and no base material is added or reolaced.
See NC.NA-AP.ZZ-0028(Q), code Job Package, for additional clarification.
i i
Nuclear common Page 14 of 16 Rev. 2 i
l t
NC.NA-AP.ZZ-0020(Q) 1 6.6 R2ntine Maintenance Activities - Activities such as aojusting, crimping, grinding, lapping, machining, replacing-in-kind, soldering, etc. which ray be controlled by directive, instruction, procedure or work standard.
6.7 Replacement (1" or less NPS Nuclear Code item!
The in-kind replacement or equivalent replacement of nuclear Cods item (s), specifically, piping, valves, fittinge and associated supports la cr less NPS.
j 6.8 Use-As-Is - The determination that a nonconforming i
C/S will be able to meet all its engineering functional requirements, including performance, maintainability, fit and safety, either permanently or for a pre-established length of time without any further corrective actions.
7.0 REFERENCES
7.1 HCGS/SGS Updated Final Safety Analysis Report, Section l
17.2.15 7.2 NRC Generic Letter 90-05 Guidance for Performing Temporary Non-Code Repair of ASME Code Class 3 Piping 7.3 ASME Boiler & Pressure Vessel Code,Section XI 7.4 NC.VP-PO.ZZ-0010(Q), Operational Quality Assurance Program 7.5 Nuclear Department Repair Program Manual 7.6 Cross References 7.6.1 NC.NA-AP.ZZ-0008(Q), Control of Design and Configuration Change, Test, and Experiments 7.6.2 NC.NA-AP.ZZ-0009(Q), Work Control Process 7.6.3 NC.NA-AP.ZZ-0011(Q), Records Management Program 7.6.4 NC.NA-AP.ZZ-0013(Q), Control of Temporary Modifications 7.6.5 NC.NA-AP.ZZ-0028(Q), Code Job Package 7.6.6 NC.NA-AP.ZZ-0050(Q), Station Testing Program 7.6.7 NC.NA-AP.ZZ-0059(Q), 10CFR50.59 Reviews and Safety Evaluations i
4 f
Nuclear Common Page 15 of 16 Rev. 2
____._m NC.NA-AP.ZZ-0020(Q) l 7.7 commitment Documents i
7.7.1 Hope Creek l
CD-525E (IR 86-132)
CD-843F (NRC Generic Letter 90-05) 7.7.2 Salem C0312 (NRC Generic Letter 90-05) l i
i Nuclear Common Page 16 of 16 Rev. 2
I e
i FORM NC.NA-AP.22-0020-1 l
DEFICIENCY REPORT l
DESCRIPTION HC_ S1_ S2_ SC_
WR/WO #
DR #
Non-DR _
Component Code Item?
Y_
N_
Sys/ Code Model #
Serial #
l 1
I l
l 1
Initiator Date LCO #
Exp. Date Time SNSS/NSS Date DISPOSITION REPAIR REPAIR (NUC. CODE ITEM)
_ REPAIR (ASME VESSEL)
USE-AS-IS _ REPLACEMENT (1" or less NPS NUC. CODE ITEM) _
i OTHER 10CFR50.59 Safety Eval. Required? Y _ N _
10CFR21 Applies? Y _ N _
Design Change / Temp. Modif. Required? Y _
DCP/TMP #
N_
Future WO Required? Y,,
WO #
N_
l System Engineer Date REVIEW
- Req'd for selected SQA Date Code items
- ANII Date ACTION COMPLETE DO NOT IMPLEMENT UNTIL REVIEW SECTION IS SIGNED Job Supervisor Date SQA Date
- ANII Date SNSS/NSS Date Nuclear Common Page of Rev. 2
- t
.l b
'.l'l
.I!
- li!
I I
It li e
2 C
ES v
e TD AI R
E T
- G 0O 2L 0
0T
- R N
ZO O
f P
o Z. E I
T PR P
A I
- Y R
AC C
N. EN S
e E
g CI D
a NC P
I MF RE OD F
T If N
U I
f OW/RW n
om mo f
C RD r
1 ae lcu N
1 i*
1
t..
Shutdown Safety Assurance Team TEAM LEADEA B ion 0 Gradv Phil 0*Danell s
Safety Review Forundo Rscart I
I I
I Maint -
Maint -
Lacens1ng Plannang Engineer ng Operatsons Conieois Nchan cel Dave 5 sth 8 tin O'Brien Harold Irenka Bob Olsen Ron Heaton Lou %catt I
- ~ - -
1 STOP WORK ORDER i
4.0.5 PUMP AND VALVE INSERVICE TESTING _
~
Quality Assessment Audit 95-012S, inservice Testing, has identified significant deficiencies in the content and conduct of the Salem inservice Testing program...
These deficiencies are being reported on generic Licensee EvenLReport no.
i 272/95-18-00.
~ "'
i The Audit consisted of a review of a sample of components'in fdur'sysTed6," ""'""
- Residual Heat Removal, Component Cooling, Aux. Feed and Service Water.
- The generic implications of the deficiencies have no' been fully investigated to date. Therefoie, continued testing without the direct u.olvement oIthe In' er' ice Test Engineerplaces therStations at risk of.further violatjons which sv would be added to the LER..
The Mariager-Quality Assessments Salem is placing a Stop Work Order on the current process for conducting 4.0,5. Pump and Valve Inservice Testing.
The InseMee Testing of Pumps and Valves, will continue. However, tests may only be conducted with the written permission of the Inservice Test Engineer, on a test by test basis, until this Stop Work Order is lifted. This.pcovision.is.to provide an additional barrier to prevent inappropriate testing prior to establishing formal controls.
Authorized by:
Ahnw%sW6 ff The Mana#r-Quality Assessments Sale'm ' Date A
edg Operations Manpalem Date m
7-24-96~
Manader-Salem Station Planning Date
/
Technical Manager Salem Date I
i 1
- PA *,a cc'.on eccT_vn_,,ess
l Kev reasons for Stoo Work Order
)
The inservice Test Proaram is reautred by Section.4.0.5. of the Technical Sr,sG;caticas and 10CFR 50.65a l
Test Methods are not in &>xrdence with ASME Selon XI Code or Federal i
Reaulation reauirements.
l Instances where we are not maating commitments to the NRC for Generic l
Letter 89-04.
instances of inadequate testing methods e
Aux. feed pump - full flow test, " clapping for duo-checks" inadequate control of pump baseline methods (22 RHR) e l
Test method not adequate to determine full flow capability as required by l
Tech Specs Inadequate control over pump. test line-ups to ensure test repeatability as l.
required by the ASME XI l
Procram documentation is not adenuete.
Incorrectly calculated acceptance criteria; 11 Component Cooling # ump was not placed in an increased testing frequency due to miscalculation of acceptance criteria. Therefore this pump is overdue for its 4.0.5.P test.
i issues of incomplete documentation and missing justification for testing e
acceptance criteria.,.
i No document control process for pump baseline data sheets.
e Schedulina and Test Performance is not effective.
Currently 22 and 23 Component Cooling Purnps are overdue for their 4.0.5.P tests therefore we can only take credit for one CC pump (21).
No formal program or process to control the performance and prioritization of cold-shutdown testing for valves.
i 2
,.n._
~....., ~,..
.,---2-,
e
\\
i Lgf t,han adecuate control of test instrumentation.
i
\\
\\
Instances where current testing methods do not meet ASME Section XI for
{
instrument range.
/
Procedural control does not exist which ensures that in plant M&TE whj.ch is: -.
e used for 4.0.5.P testing that is found out of calibration is reported to the IST' Engineer to permit test result evaluation.
ti-v..'s,
.s c.
~~
l 1
I
- t a =4 s
e
....y,..
l
~.. *. u.. :.,
I
~.
I r
~
- 4.
,s 4
l
.*.'.s..'..,
I j
l l
l l
l I
i t
I
\\
i I
I t
3 PO*d rarn. p ra Ccc T.T ra.W
Specific Actions required to be comolete orlor to liftina this Ston Work I
D This willensure thatProcess controls exist to establish a central point
(
i The IST Engineer is notified prior to the performance of any 4.0.5. test.
)
Testing procedures are reviewed to confirm that the methods are suffi demonstrate operational readiness as required by Technical Specificatio and ASME XI.
Acceptance criteria for pumps and valves is revalidated.
e a process for adequately docurnenting testing acceptance criteria changes is established. '
~~
Process controls exist that ensure that M&TE used for pump and valve i
meets ASME XI Code requirements.
t
}.
Process controls exist that ensure that out of calibration M&TE used fo i
and valve testing is reported to the IST Engineer for test evaluation.
4 The IST Engineer is in the review' process for changes to 4.0.5. testing i
procedures.
j
)
1, Subseauent Lona Term Actions 1
Verification that we are meeting our commitments to Generic Letter 89-04.
The IST Manual is reviewed and updated to reflect NRC commitments, des basis requirements and limits, and responsibilities are defined.
Develop a formal program or process to control the performance and prioritization of cold-shutdown testing for valves.
4 Establish an effective document control process for pump baseline data sheets.
j i
i l
f SO*d em:/ a cf:AT-T A-CYN I
?
U C
y$/7s' INITIAL MEETING BETWEEN PSEG AND NRC SALEM ASSESSMENT PANEL - AUGUST 3,1995
(/[6C-1 ( Q (W }
{%1-Id L..
%g p, f/ysuSM OBJECTIVES
- Cr(9 %
1.
Initialinterface and identification of key personnel 15Y gM 2.
Review of the first Salem Assessment Panel Meeting A
kak 3.
Establishment of future interface process
- Salem Assessment Panel / Public Meetings d5 O g
f b
- Individual Contacts oa% ibs
- Other Communications.
4.
Verify inspection Coordination (including RATI) 5.
Discuss Alignment on restart issues
- NRC Salem Restart Action Plan
- 46.e / stems selected for system readiness 6.
Discussion of' CAL Action items 1 and 2 7.
Rev sw next weeks agenda - 8/9/95 NRC Plant Tour and 8/10/95 Restart Process Meeting
- par 1
-QeshdQwv0 l
l 1
l.:
SALEM ASSESSMENT PANEL ACTIVITIES 1
MET INITIALLY ON AUGUST 2,1995, TO:
l e
REVIEW IMC 0350 RESTART PROCESS AND ISSUES CHECKLIST FOR STATUS AND APPLICABILITY IN PREPARATION OF NRC l
RESTART PLAN 1
l e
REVIEW AND APPROVE SALEM SPECIFIC l
RESTART ISSUES LIST DEVELOPED BY THE j,
SENIOR RESIDENT INSPECTOR 1
e REVIEW STATUS OF PSE&G RESTART PLAN l
e IDENTIFY NEAR TERM INSPECTION PRIORITIES
- CORE OUTAGE COVERAGE'
- EVALUATIONS AND VALIDATION OF PSE&G READINESS ASSESSMENTS TO DETERMINE OUTAGE SCOPE e
DISCUSS INITIATIVE TO SEEK INPUT FROM NEW JERSEY ON PROCESS u. -
w--
l NRC POSITION ON SALEM - 6/23/95 l
l The safety performance of the Salem Nuclear Generating Station was reviewed during the January 1995 Senior Management Meeting in which it was decided that NRC Senior Management Meeting should meet with the PSE&G Board of Directors.
On March 21, 1995, the NRC's Executive Director for Operations, Director, Office of Nuclear P9 actor Regulation and the Regional Administrator, Region I, l
met with the licensee's Board of Directors to' communicate NRC's safety concerns regarding the performance of the Salem 1 and 2 (see attached meeting summary). The board members and company officers confirmed their commitment to improve performance of Salem Station. Since the board meeting, the i
I licensee has revised their corrective action plans based upon their critical f
self assessment of their safety performance, is taking action to improve their site management team, and has established higher standards of performance and accountability for station staff, particularly licensed operators. On May 17, 1995, the licensee voluntarily shut down Unit 1 to resolve concerns with i
switchgear room supply fans, initiated a comprehensive multi-discipline I
evaluation of all outstanding maintenance issues, revised and refocused the engineering support organization, and initiated a high level review of the problems which led to the Unit 1 shutdown. These actions are indicative of the corporation's commitment to improve performance at Salem Station.
l In June 1995, NRC senior managers discussed PSE&G's actions since the last SMM l
and concluded that licensee senior hanagement was taking action to improve performance at Salem and that facility performance was not trending adversely nor did it warrant placement on the NRC's problem plant list. Licensee management action since the June 1995 Senior Management Meeting to keep both
?
/
l l
_u._--
i
,i h
!j i
i a
4 1
l F
4 l
I J
J l
f i
4 i
i e
a 4
i 1
4 1
i 1
]
M
. 2-Pnp.,
e s.
,,L
.e
FROM HUC EXTERHAL AFFAIDS 8.
7.1999 13:35
... o (MONJ OS. 07' 55 37:'3/ST. 37.H/NO,3*>61467'? P 3 annu arvengtX FOR SYax m:M ar4ngNyas gryyp,w parsENTATinN$
%/
MONb4Y AL)GW1'141Ml LOCATION-SALEM Tsc
(
11:06 - Llo6 CAV GULasANFAEWA=FMKKKNTS 1 00 - 3:00 GEM PAUL WORAIGNYO MtEEFNTER 2:0e -atoo CAN ALAN JORNSON.htBENTER t
I TUNDAY AUGU$r25,8Ms LOC 4T10N S4LKhf TSC l
11:00 - IrCO GT (U/3) l D.EDLASDr$53/YUAY BEATIA MtESENTKJtX 1:00 2100 TO MATT OR11CELLE -MtKEENTER 2400 3:00 Ms MIKE MALEY MLAT&YTEA J:00 4:00 RVI.!S
$ANDYJANNETTY MtEf2NTA3t t
l MSDN83n4Y AtJGtMT16,IME LOCAtl0N-SALEM 15C
~
i i
12:00 D00 Cav j
W JACK CUREAll-PRMENTER 1890 2 tot CR WAYN1 CEOROMANSKI-PA83ETT5K i
2!00-3:00 N&tNCORE EJEA FORD -Mt#EKNTEJt 4.40 4:00 RC8/RPI DOMDGC SEEA.FRATENTEA
\\
THintSA4Y AUQWT1t,2M5 LOCATION-sal 2M 15C 13:00 - h00 BCTR/F5
- 1. TBDhMSSERRY -MtKSENTKK bee - ziet RMS
- DiORSEM-MtBSBNTER 2:00 - 3.46 BAEKY JOEN PERafSE-PRatsN7EA nt/b4Y.400U5T18. IN1 LOC 4TJON SAIAMTBC l
12:00 - 1eos AF CARL TOO(-MtaEEWTKA rs 100 140 CF l
WE311 NOM 0U51.FxtJmVTEA I
\\
I
s FPON HUC ENTERHAL AFFAIRS g,
7,g99g g3,34 p.
l l
v' l
l To:
Charles Marschall 935-3741 (FAX) l John White (610) 337-534(8)
(FAX) l 1
From:
Dana E. Cooley (609)339-7427 (Voice)
(609) 339-7453 (FAX) l l
The latest MRC Five-Day Lookahead.
l Please call ifyou have any questions.
l i
l l
l 3
l c.
s
l FOOM HUC EMTERNAL AFFAIRS 8.
7.1999 13,3o P.
2 c
MRC Five-Day Look-Ahead (4:00-7:00 PM - Salem GM's Conference Room unicss otherwise noted)
HIRhWTH &:<:nn':!Prc '. G}:Mir'?l-N em
'RlPissenter:
--...t-
-tl Monday, August 7
' Outage DCPs (S001 Ashok Moudgill & Project l
turbine runback, Managers l
l HEBA/MEBA, Feed Ring AJ-tube Mods, Non Safety 14 AWO Cable, and to Others)
Operator Workarounds JefrBeattle 4 KV System Ray Chranowski i
l 13KV System Vijay Bhatla 230/460 V System
,,R_,a,y,,,Chranowski Tuesday, August 8 ConAguration Walkdown George Englert Plannhtg DEF Review planning Craig Lambert l
ControlRoom Annun/Indic.
Bob Watson /Len Rajkowski NIS Excore Jim Grimm d
Component Cooling Wayne Choromanski Aux B1,,dg Ventilation Jack Curham Wednesday, August 9 Unit 2 Turbine Rotors Bill Schultz j
Appendix "R" Issues Bill McDevitt/M. Burszteln Condensate and Feed W. Lowry/S. Robitzki Safeguards Eqt Cabinet Dominic Shea Bleed Steam Matt Orticelle Thurssday, August 10 Mech Maint ATS Items Mike Metcalf l.2,5/,,2,,,3,,g,S,,y s, tem James Schubert _
Friday, August 11 RMS Issues John Cicconi I15 VAC Bruce Focht Service Water Jim Barnes Circu!ating Water Bob Swartzwelder
[
/
c.
I i
d l
8n/95 1:22 PM
j FROM HUC EXTERNAL AFFAIRS 8.
7.1995 13:35 P.
3
...... M M..___ _.,..._.
ut n J.'::o' ur 01:521.y0. 3glimv; y3 4
numa scenrmn a rout svm rz.w artnwrma urvirw ymmmirArrows W
MONAer Accar1, ten i
J 1.ocArso#-suswisc
}
ism -ae, Cms I
saA.LowRY/srtvt mostrzsar. pasuvrJtas
'(
renantr Atlocara, ins I
LOCATION. SMMstC tL M - bet SW JDiBARNES. #AMENTER 4
tm 2m Itarsevoc J.SCIUBRRT tyts3sNTEA
{
2:00 - 3m CN/CI l
DOMDUC 8EEA-Mts3ENTsA i
MCDMMEDAY At/GEMr9, AHi IAM;4T10N $ALEM t.9c r
l 4
12M 1:00 RER i
JDEN ERNARD -MtsANrEA 1.
1:00 100 CW
{
BOB SWARTEWELDER-Mts2NTFJr 2:46 Se40 115YAC i
BatTCE FOcsT PAMENTEA Y***
I.
1 1
M TMLosEAdv stMlaras 2005 LOCATJON-2A12At-ine
- * * ~ ~ '
i c
1 4
13:00 1d0 FEY i
GUIJEANPAEWA PAMENTKM i
1:M = 1:M FR$
3 IJSA FORD -#REENNTAN i
SWO a 3 tee CA/BA 3ILL RODGERS -MtMANTER l,
i, MtGL4Y At/GRArt11,1M1 LOCA170N.2M.RW15C 4
13:00. trae Si JORN ERNARD.MtaEsNTIa Im -See FAss sFEER-Mtas*NrK4 2:00 - 2m CYCS 1
CARLTRIM. StMENTER 8
EA11MtDAY ACIQtl5T1J,1MS M3C4 Tion 34LBWTEC
/
thee - 1100 BCP/SSF f'
1 JOHN FEstU55.MtantNrKA i
1:40 2:00 BEC I
SANDY JANNETry-Mtarg#rsR i
d 1
]
1 k
l I
r.en
,,ue c m a,m arr m s
- e. a. n,.
a.u
- r. i
['
MRC Five-Day Look-Aliead (4:00-7:00 PM - Salem GM's Conference Room unless otherwise noted) l~^
"Date;
'I Time l Topic l
Presenter l
Thursday, August 10 4.00 Salem Facilities Rer ovations Steve Maginr.is 4:15 Dleed Steam Matt Orticelle 4.45 Safeguards Eqt Cabinet Dominic Shea 5:15 FW Condensate / Boiler Feed W. Lowry/S.Robitzski 5:45 Unit 2 Turbine Rotors Bill Schultz i
6:00 MRC Charter Revisions Dana Cooley,,,,,,,,,,,,
Friday, August 11 4.00 RMS issues John Cicconi j
4:30 115 VAC Bruce Focht 5:00 Circulation Water Bob Swartzwelder i
5:30 125/28 VDC Sy_s,te,m,,,,_
J. Schubcrt Monday, August 14 4:00 Diesel Generator D.Kolansinski/R.McLaughlin 4:30 Post Accident Sampling Sam Speer 5:00 Fuel Handling Lisa Ford 5:30 Turbine Building Fan Issues,,,,,,,,,,,, George Boghosinn Tuesday, August 15 4.00 Containment Painting Ul/U2 Bill Hunkele 4:15.
Safety injection John Erhard 4:45 Fuel Handling Building Vent Gulshan Pahwa 5:15 Controlled Air / Compressed,,d,r,,,,. Bill Rodgers Wednesday, August 16 4:00 Appendix "R" Issues B. McDevitt/M.Burszteln 4:30 Main Generators Ul/U2 Paul Morskinyo 5:00 Residual Heat Removal John Erhard 5:30 Containment Building & Pen Alan Johnson l
\\
1(
ano/95 10.52 AM c
AUG-15-1995n u c m a,08: 5,.1 h
p raun m,, 6,,,, %
eo MRC Five-Day Look-Ahead (4 00-7:00 PM -Salem GM's Cortference Room unless otherwise noted) 1 TMM&n*ts%& h%nbli.9tM!&MWMonicMNCNW+*WN12%ST> AMT_W
, Monday, August 14 4:00,__Tu_rbin,,e,,,, Building Pan issues,,,,,,,,,,, G.org,,g;=p.mL.
Tuesday, August 15 4:00 ControlRoomInstnstnents Dominic Shea 4:30 FuelHandling Building Vent Outshan Pahwa j
5.00 Control Alr/ Compressed Air BillRodgers
)
,,,,,,,,,r,gainment,,PaintingJJ 1/U2 Bill Hunkele Co 5:30,,,
RittBraddick/Mo Bursstein Wednesday, August 16 4:00 Appendix"R" Issues D.Kolansinski/R.McLaughlin 4:30 Diesel Generator 5:00 Main Generators PaulMoraldnyo 5 :30,,,,_
Servi,c,,e,,,,Wa,ter Jim,B,,,_arnes
.. Thursday, August 17 4;00 Mech. Maintenance ATS Items Mike Metcalf 4:30 ResidualNeat Removal John Erhard 5:00 Oss Turbine U/3 Dave Kotanninski/VijayBhatia 5.,:,3,, 0,,,,,,,T,u,rbine Generator Iggt,O,,,gjoelle Friday, August 18 4:00 FuelHandling System I.AssFord 4:30 ElectricHydraulic Control Sandy Jannetty 5:00 Chilled Water Wayne Choromansid 5:30 BillOfMaterials Validation Lou Santonastaso i
l l
I 5/14/93 11:34 AM i
d TOTAL P.02
'2
~
a SCHEDULE OF SYSTEM READINESS REVIEW BOARD PRESENTATIONS t
WEDNESDAY.
THURSDAY FRIDAY 8/2/95 8/385 8/485 5
i 12:00 - 1:00 4KV, 12:00 - 1:00 CAV 1220- Id)0 CN/BF 230/460V I:00-2:00 CC 1:00 -2:00 ABV 2:00- 3:00 CVCS 3:00 -4:00 BS 3.00 - 4:00 CS LOCATION 2ND FLOOR "B" BLDG.
HOPE CREEK CF. RM. "A" (across from elevator)
E.
S n 1
b
Project
Title:
Unit 2 System Readiness Review Salem Station
.g l
Auqcst l
Septernber October I
i (D
Task Nur'e l Dwr Systere Respecsstet, 30 l 6 l 13 l 20 l 77 l 3 1 13 l 17 l 24 I l 8 l 15 l 22 l 29 l
m 1
4KV System -instaal 3Sd 4KV M.Mortarufo Slit W22 18 CAV systern -Innias 25d CAV P.UDocruell Br18 y S/11 y
ggg 13 OG System -Irdtial 25d OG SpivaktMortaruto gftg y
y 32 HSD System-Initial 22d HS3 E Mortartdo gfig v v gg l
g,12 41 MSEXCORE System -Innial 24d NIS4XCOR E Mortaruto gigg y
v 3 fig Se RHR $ystem-Initial 26d RHR P. O'DomrieN gfig v y
l SS SF system-Initial 2ed SF P.OVormes ar1s F
~ sit 2 Se SW System -Initial 29d SW G. Spivak grig
, gfgg 77 4tict230 V AC System -Irinial 26d 489/230VAC M Mortarule 3,28 y y s/22 36 ABV System. Initial 15d A8V P. O'Donnell St1 SME SE CAISASystem trglial 19d CAAiA G. Sptwak gjg,
, gfgg i
104 Cf.N System-initta) 18d CAN G. 5pivak gfg v gf93 113 CH Systern -InRhet 154 CM P. OVermeR gig 3f33 Q
si20 c
122 CS $ystem-Ininal 20d CS P.Otor:mes sti y
L" 131 CVC System -Irdlial 20d CVC P.ODo M ggg v 3;20
]
y 140 ENC Systern -Intual 1ed EHC E Wortaruto sfy v yjg v
14S G EN System -taittal 29d GEN M.Mortarulo S!1 y y 300
- o a
ha RCPASSP System-kiitial 22d RCPJSSP E Mortarulo St1 y
$222 y
167 TB System-tnalat 19d TS G.SF.C sfi y y 3,19 E
-h St19
-s 175 TGITL System-Initial 19d TG G.Spivat Sri y 7
2 186 124128W DC -trutial tid 12512tV DC M. N sf4 3 14 h
194 SEC Systern -InlNat 16d SEC M. Mortatulo 34 afgg N
243 13KV System-butiat led 13%V E pertatuto We W25 212 CNtBF System.Intbal 19e CMBF McriarulotSpivait 52 S(26 hy CW G.Spivan gg 224 CW System-lettlal 20d j
01
_ 9
~ ~ ~ ~
Task Surnmary RodedUpProstoss usuuuuuuuuuumuuur musum Rdied Up Task N
N Prc[ect SRRP Schedule P ress 1
Date. FriS(It95 Westoce RcDed Up Miestone {f l
ta2
O lo.
1 Project
Title:
Unit 2 System Readiness Review Salem Station
- W;:::
l August l
SesAs October i I 3 l 10 l 17 l 24 1 l 6 l 15 l 22 { 29 M
ID Tasn Marrie Our System Responsititity 30 l 6 l 13 l 20 [ 27_,
f S!B 233 FMV System. Initial 18d FMV P. Overmen S/25 242 HT Syste.li. kinian 18d HT M. Mortaruto 3;g 3;26 151 NIS-NCCRE System -Irvital 204 NIS-INCORE P.OVonneu t/27
, 318 369 RCIPR!P6 System. Initial 21d RCIPR!PS P. OVonneII l g,,y g,gg i
145 RCS/RPISystem In.tlat 19d RCSIRPI M. Mertarulo 9/S S;2E l
273 RM $ System-httkl 1ad RMS M. Mostaru%
S/12 S:29 237 SJ System-Initial 17d SJ P. Overmen S/12 S;28 23s AF system-: natal 154 AF P. ODennell etts Sc3 305 Itailey Rads (Jntt 2 -Intrial tSd BAILEY M. Mortaruto S:15 tsc l
3 14 BS System-Initial 15d BS O. Spivak St13 S/23 323 CSV Systern-Irdlial tad CSV P.OVonneH W1$
10!2 332 CC Systern -InitM 18d CC P. 01)onnett gjgg gg 341 CP Systern -inRial it:5 CP F. CVonnell S/15 1012
-4
]
350 FMS System -Initta spd FHS P.OVonnes S115 ter3 353 MS System-Initial 1Sd MS G. Spivak g,$g igf3
,g 368 RV1.IS System-Initial 29d RVLIS M. Me.tavulo Sf15 1 314 377 116V AC Systern-Inmai 14d 115V AC M. Mostaru?o S/23 10/6
'r$
388 CRCI Systern -Influt 12d CR/Cl M. Morte g/29 M ictie C
t 21 z
f*
8 i
u M
3
~.$.
i l
,3 Summary RoDed up Progress Tad i- ? *':_ J.
Prefect SRRP Schedule P
RN WTad
- *: ' '.. ~
,,3 Da e. FriS/1f95 Llaestone RcGedupMI!estone Q l
2 et 2 I
i
SEP-10-1995 13:37 P.02 MRC Five-Day Look-Ahead l
(4:00-7:00 PM - Salem GM's Conference Room unless otherwise noted)
Monday, September 18 -
4:00 Human Performance Action Plan L. Newman 4:30 Electrohydraulic Control S. Jannetty 5:15 Containment Building & Pens A. Johnson /S. Speer 6:00 Service Water J. Barnes 1
6:45 Erosion / Corrosion B. Montgo,,,m,,, ery,,,,,,,,,,,,,,,_
Tuesday, September 19 4:00 Salem U/1 Restart DCPs C. Nentwig 4:15 Control Air / Station Air B. Rodgers i
5:00 Safeguards Equipment Control D, Shea 5:45 In-Service Inspection L. Lake /M. Conroy 6:15 Reliable Maintenance Action Plan J. Laughlin Wednesday, September 20 4:00 Turbine Generator M.. Orticelle. ;f n
4:45 Turbine Bypass M. M ale'y l
5:30 Equipment Reliability Action Plan J. Ranalli
_ _ 11,5_,,Corrective Actio,,n Action Plan J. Morriso,n 6
t
'Ihursday, September 21 4:00 Containment Spray T. Hoeg 4:45 Chemical & Volume Control C. Timm 5:30 Main Generator P. Morakinyo m
l 6:15 IAC DCRs Backlog.
V. Fregonese l
6:45 Engin,e_er,,ing,,P,e,,rformance Action,P, lan,,,,,, J,, R,ana,lli,,,,,,,,,,,,
Friday, September 22
__ NO MRC MEETING PROPOSED ACTION PLAN MRC REVIEW SCHEDULE e,
E.W 4: y nn, ' -
TF ~M E # i,'1 Uhi.h i.ta:nw? Z,iMTMMM9QfM l
1 j
Monday,,,, September 18 4,
/4 Human Performance Action Plan L. Newman l
Tuesday, September 19,,,,,,,,,,,,fd~ ',R,, piable M,aint, nance Ac,t,lon,,,P, lan __,,,,,LL,a_u,,glgin e
, Equipment Reliability Action Plan J. Ranalli Wednesday, September 20 CJ *t l
C*
Corrective Action Action Plan J. Morrison Thuraday]%bber 21 p!/h Engineering,P,,erfor ance
~
~3~~
itio~~~ Plan [
~J,Jjrl,,i, l'lI
~~~~~~[~~~
~~~~
n l
F,pda,y,,,S,eptember 22
, N.,,0 M R,C M E E,,, TIN,,,G,,,,,,,,,,,,,,,,,,,,,,,,
l Monday, September 25 Y Operations Action Plan C. Bakken I
c 54 Work Cont'ol Action Plan E. Harkness l
- Training Action Plan - take credit for NTOC Review.
- Outage Action Plan - business issues, not a Restart item.
I
~
09/ft/P3 I
l f
TOTA P.02
MRC Five-Day Look-Ahead (4:00-7:00 PM - Salem GM's Conference Room unless otherwise noted)
Ekku is.:HiDueddie$hisliiTinl@li$iNiisishliM?.W#iSiiMMe#lW!l!@ENuiMPresesibt#pel Monday, Sept 5EEer 11 4:00 ResidualHeat Removal R. McKinley 4:45 Diesel Generators D. Kolasinski 5:30, MSR Drain Line_
A_. Moudgill/K. M, athur Tuesday, September 12 4:00 NonRadwaste Valve Seat Replacement B. Bovankovich 4:30 Conf. Control Related Incident Rpts.
O. Englert/R. Klosek 5:00 BOP Delta Work G. Spivak 6:00 Delta Work M. Rancheck Wednesday, September 13 4:00 Hot Shut Down Panel D. Shea 4:45 Equipment Qualification (EQ)
A. Blum 5:15 Self Assessment Action Plan N. Conicella 6.15 Delta Work M. Rancheck
~~~
~~
Thursday, September 14 4:00' Spent Fuel Cooling L. Ford
~
~
4:45 Control Area Ventilation G. Pahwa 5:30 Electrical & I&C Delta Work M. Mortaruto 6:30 Corrective Action Action Plan J. Morrison Friday, September 15 4:00 NIS-Excore J. Grimm 4:45 125/28 VDC J. Schubert 5:30 Long Standing Equipment Problems D. Gamer 6:15 Work Control Action Plan E. Harkness 7:15 Reliable Maintenance Action Plan J. Laughlin 1
l l
l 1
f i
1 l
. 9/11/95 -
3:22 PM 1
e i.
l 20*d SS890 S66t-Et-d3S
CO'd ~H101 l
r l
PROPOSED IMPACTPLAN MRC REVIEW SCHEDULE Wi8iisd1?Diits!!iti:MMili'0:4TiseitsnuMkhMWiT6siiMin sLine.!#6tp%!.T;i9i Fr'esenter W Cl Wednesda.1 S_eptember 13
.Se.lf Assessment Acti.on P. lan _
N. Conicella
. Thursday, Septem_ber 14 C._or_r.ec.tive Act.i.on Action Plan.
. J _Morri._so.n _
1 Friday, September 15 Work Control Action Plan E. Harkness
_R. e. liable Mai.n_tenance Action _ P._lan l
Monday.4.._S.ep-temb.er 18 Human __P..e.r_fo.nnance Action ~Pla_n..
J. Laug.hl.in L. N.ewman---
Tuesda.y, September 19
_Operat. ions Action P_lan C. B._akken Wednesd_sy.a.Se.ptember 20 Equipment Reliability Action Plan J. Ranalli l
Thursday, September 21 l Enoineering Performance Action Plan J. Ranalli i
- Training Action Plan - take credit for NTOC Review.
- Outage Action Plan. business issues not a Restart item.
)
l l
l g
g,
- * [ 4'
.t
.?
- li ba i,i '
fs.
3 i '! ' & lks w, g g.
u.
CO*d N N -U -"
_w. n,,
a.w v.e2 MRC Long Term Outlook i
Nl Mci WDktePMW W: d vrinfet/w
-~
": Topic l
Presenter l
Thursday, September 7 4:00 Appendix "R" Iswes M. Bursztein 4:15 MS DriA/RCS Excess Cool Down C. Wi!!iamson 5:00
__ Ope,,r,a, bility Determinations _
, _ B. O',Gr_a,dy Friday, September 8 4:00 Maintenance Control /RMS Dacklog R. Risley /B. Watson
_5,,;00 Collective Impa_ct o,,,f,,,,U, nit 1,,,,D, cps
,, M. Rench,eck,,,,,,,,
Monday, September 11 4:00 Hot Shut Down Panel D. Shea 4:45 Diesel Generator D. Kolasinski 5:30 MSR Drain Line A. Moudgill/K. Mathur d' 6:15 Work Control Action Plan' E. Harkness t
Tuesday, September 12 4:00 Hagan Refustishment A Replacement M. Annon 4:30 in-Service Inspection L. Lake 5:00 Outage Action Plan R. Antonow
,_,r 6:00_
Conduct,,of,_O,perations Action Plan _
C. Bakken l
Wednesday, September 13 4:00 Spent Fuel L. Ford i
4:45 Equipment Qualification (EQ)
A. Blum 1
A 5:15 SelfAssessment Action Plan N. Conicella 6:15 Re, liable Maintenance Action Plan J. laug,hlin Thursday, September 14 4:00 Residual Heat Removal R. McKinley l
4:45 Co.itrol Area Ventilation G. Pahwa i
A-5:30 Engineering Performance Action Plan J. Ranalli 6:30 Cor, rec,1,ive Acti,on Action Plan _,,
J. Morri, son Friday, September 15 4:00 NIS Excore J. Grimm 4:45 125/28 VDC J. Schubert 5:30 Long Standing Equipment Problems D. Gamer
{
1 4-6:15 Egu,,ipment Reliability Action Plan M.,Re,,_ncheck Saturday, September 16 12:00 Service Water J. Barnes 1
12:45 Chilled Water W. Choromanski 1:30 Auxiliary, Building Ventitation J. Curham l
Monday, September 18 4:00 Electro Hydraulic Control S. Jannetty l
4:45 Containment Building & Pen A. Johnson 5:30 Erosion / Corrosion B. Montgomery l
6:15 Jjuman Performance Action Plan
,,L. Newman Tuesday, September 19 4:00 Control Air / Compressed Air B. Rodgers 4:45 Safeguards Equipment Cont.
D. Sima
/. -
5 30
_ Training Action Plan J. McMahon
~
l Wednesday, September 20 4:00 Turbine Generator M. Orticelle 4:45 Turbine Bypass M. Maley 5:30 Main Generators P. Morakinyo Thursday, September 21 4:00 Containment Spray T. Hoeg 4:45 Chemical & Volume Control C. Timm 5:30 I&C DCRs DackLog V. Fregonese 6:00 Vendor Technical Documents G. Englert/C. Lambert Priday, September 22 4:00 13KV V. Bhatia 4:45 RCP/ SSP J.Pehush 5:30 PM, P,,,,rogram DackLog,,,,
M. Metcalf Monday, September 25 4:00 4KV/460/230 VAC W. Choromanski
{
4:45 Heat Tracing B. Foht 1
5:30 Fuel Handling,B_uild,,ing Vent.
_G. Pahwa Tuesday, September 26 4:00 RCS/RPI D. Shes 4:45 Condensate & Feedwater Systems B. Lowry/S Robitzski 5:30 Control Room / Aux. Dldg. Ventilation D. Shumaker l
Wednesday, September 27 4:00 NIS Incore L. Ford 4:45 Circulating Water B. Swarizwelder l
5:30 Comm rcial Grada D,J.dic: tion 1 B. Beard l
Thursd:y, September 28 4:00 Safetyinjecti:n R. McKinley 4:4S_ RgR/P S_,,,,,,,,,,,,,,,,_,,_,,,,,,,,,,
Friday, September 29 4:00 Dieed Steam & Hrttr Drains __
,,&,Lembergy,,,,,,,,
M. Orticella 4:45 Auxiliary Feedwater C, Timm 5:30 Radiation Monitoring System J. Grimm i
l l
l TOTAL. P.02 I
l I
I i
I 1
i i
i 1
}
l l
i i
1995
~
l EARLY EARLY OAIG TOTL AUG l
SEP l
OCT START FINISH DUR FLT' 21 28 4
11 18 25 2
9 16 23 30 OPERATIONS (010) 1010-0005
.14AUG95 31AUG95 18 9
JEVELOP CONOUCT OF OPEAATIONS ACTION PLAN I
0 010-0010 l
1SEP95 31AUG95 0
9 SUBMIT CONOUCT OF OPERATIONS ACTION PLAN TO MAC j
0010-0015 5SEP95 5SEP95 1
9
'MAC REVIEW CONOUCT OF OPEAATIONS ACTION PLAN EhkACTIONPLAN&SUBMITFORMAC'APPA0VA 6SEP95 7sEP95 2
9 L
0010-0025 l
8SEP95 8SEP95 1
12 MAC APPROVE OPS ACTION PLA'N l
ENGINEERING (030) idAUG95 28AUG95 15 14 JEVELOP ENGI I
EAF0AMANCE ACTION PLAN l
0 030-0010 29AUG95 28AUG95 0
14 SUBMIT ENGINEERING PEAF0AMANCE ACTION PLN TO MAC 0030-0015 31&UG95 31AUG95 1
14 MAC AEVIEW ENGINEERING PERFORMANCE ACTION PLAN 1SEP95 2SEP95 2
to SE AING PLAN & SUBMIT TO MAC FOA APPA0 VAL 0030-0025 l
3SEP95 3SEP95 1
17 MAC APPA0VE ENGINEERING ACTION PLAN '
EQUIPMENT RELIABILITY (090)
RELfNILITYACTIONPLAN idAUG95 1SEP95 19 8
DEVELOP EQUIPMEN 2SEP95 1SEP95 0
8 IT 0 IPMENT AELIABILITY ACTION PLAN TO MAC AY W EQUIPMENT AELIABILITY ACTION PLAN 6SEP95 6SEP95 1
8 7SEP95 8SEP95 2
8 SE LIABLE MAINT PLAN & SUBMIT MAC APPA0VLL 0090-0025 9sEP95 9sEP95 1
11 MAC APPROVE AELIABLE MAINTENANCE ACTION PLAN LICENSING PLAN (110) bkTIATIVES 2dJUL95 8SEP95 47 3
IDENTIFY t.,1 CENSING AE 24AUG95 11SEP95 19 8
OEVELOP ACIION PLA I T GAATION MATAIX MACAEVIEWACTIONWANSSSEATAECOMMENDATIONS 28AUG95 idSEP95 18 3
AEVkW AC I 4 PLAN INTEGAATION MATRIX WITH S 12SEP95 12SEP95 1
8
'G
~
1dSEP95 27SEP95 14 0
MTGS A !
ANS S. CAL ITEMS 1,2 3 MTG WITH SAP - DIMNOSE (IF POSS) 28SEP95 28SEP95 1
0 CAL 1 -3 120CT95 120CT95 1
0 NAC AEG 1.MTG (IF AEQU!AED)' T bSfbTCAL1-3 200CT95 190CT95 0
0 COMPLETE 00CKETING SUBMITTALS FOR CAL Thf1
-3 110-3030 0 270CT95 260CT95 0
0 REGION 1 AGREEMENT ON CAL ITEMS 1,2.I 3 b!kb,!N
@ @ [*"""
PUBLIC SERVICE ELECTAIC C GAS 5.E" 1.~m l
om SALEM AESTAAT PLAN ACTION PLAN APPA0 VAL SCHEDULE
s EARLY EARLY ORIG TOTL 1995 START FINISH DUR FLT AUG l
SEP l
OCT OPERATIONS (010) n010-0005 14AUG95 31AUG95 18 9
3EVELOP CONDUCT OF OPERATIONS ACTION PLAN 0 010-0010 1SEP95 31AUG95 0
9 SUBMIT CONOUCT OF OPERATIONS ACTION PLAN TO MAC 0 010-0015 -
SSEP95 SSEP95 1
9 MAC REVIEW CONDUCT OF OPERATIONS ACTION PLAN dk ACTION PLAN G SUBMIT FOR MRC APPROVAL 6SEP95 7SEP95 2
9 0 010-0025 OSEP95 OSEP95 1
12 MAC APPROVE OPS ACTION PLAN HUMAN PERFORMANCE (020)
.n,...
14AUG95 13SEP95 31 0
DtvLLOP HUMAN PEkf 0HMANCE ACiluN PLAN
+ 020-0010 14SEP95 13SEP95 0
0
.SU8MIT HUMAN PERFORMANCE ACTION PLAN TO MAC E020-0015 10SEP95 18SEP95 1
0 HRC E VIEW HUMAN PERFORMANCE ACTION PLAN M 020-0020 19sEP95 20SEP95 2
0 E VISE HUMAN PERF PLAN C SUBMIT FOR MAC APPROVAL 3020-0025 21SEP95 21SEP95 1
0 MAC APPROVE HUMAN PERFORMANCE PLAN ENGINEERING (030) iO30-0005 14AUG95 28AUG95 15 14 DEVELOP ENGINEERING PERFCAMANCE ACTION PL AN 0 030-0010 29AUG95 28AUG95 0
14 SUBMIT ENGINEERING PERFORMANCE ACTION PLN TO MAC 0 030-0015 31 AUG95
- 31AUG95 1
14 MAC REVIEW ENGINEERING PERFORMANCE ACTION PLAN 15EP95 PSEP95 2
14 SE ING PLAN C SUBMIT TO MRC FOR APPROVAL Q030-0025 3SEP95 3SEP95 1
17 NRC APPROVE ENGINEERING ACTION PLAN MAINTENANCE (040) r040-0005 14AUG95 1SEP95 19 11 BEVELOP NLIABLE MAINTENANCE'ACIION PLAN 0 040-0010 8
2SEP95 1SEP95 0
11 SUBMII RELIABLE MAINTENANCE ACTION PLAN TO MRC QQ40-0015 6SEP95 6SEP95 1
11 MrE REVIEM ELIABLE MAINTENANCE ACTION PLAN C ]040-0020 8
7SEP95 OSEP95 2
11 REVISE RELI A8LE NAINT PLAN & SU8MIT MAC APPROVAL.
0040-0025 9SEP95 9sEP05 1
11 MAC APPROVE ELIABLE TINT ACTION PLAN ht.rt f-
$(({
U8LICSERVICEELECTRI[GdAS
[s,"on"** "*" chec* ea arma na, proiect nnisn nues o ^-
=>=taa""""'""'
SALEM RESTART PLAN RESTARI ACTION PLAN SCHEDULES
- - - ~ ' - -
D (c) Primavera S*ste*S.
X c vr+srspioisse?sor not Mx
l i
EARLY EARLY ORIG TOTL 1995 START FINISH DUR FLT AUG l
SEP l
OCT OUTAGE PERFORMANCE (050) 1050-0005 14AUG95 BStP95 26 5
KVELOP OUTAGE PEAF0AMANCE ACTION, PLAN,
0 050-0010 9SEP95 OSEP95 0
5 SUBMIT OUTAGE PEAFORMANCE ACTION PLAN TO MRC 0 050-0015 12SEP95 12SEP95 1
5 MRC AEVIEW OUTAGE PERFORMANCE ACTION PLAN 0 050-0020 13SEP95 14SEP95 2
5 REVISE OuiAGE PLAN & SUBMIT FOR WE APPROVAL r
0 050-0025 15SEP95 15SEP95 1
5 MAC APPCOVE OUTAGE ACTION PLAN WORK CONTROL (060) 8 3060-0005 14AUG95 7SEP95 25 6
KVELOP WOAK CONTA0L PA0 CESS ACTION PLAN,
0 060-0010 8S2P95 7SEP95 0
6 SU8MIT WOAK CONTROL PROCESS ACTION PLAN TO MAC 0060-0015 11SEP95 11SEP95 1
6 MAC AEVIEM WOAK CONTROL PA0 CESS ACTION PLAN Sk CONTROL PLAN & SUBMIT MAC APPROVAL 12SEP95 13SEP95 2
6 ocs0-0025 14SEP95 14SEP95 1
6 MAC APPA0VE WORK CONTROL ACTION PLAN l
SELF ASSESSMENT (070)
>070-0005 14AUG95 12SEP95 30 2
KVELOP SELF ASSESSMENT ACTION PLAN 0 070-0010 13SEP95 12SEP95 0
2 SUBMIT SELF ASSESSMENT ACTION PLAN 0070-0015 15SEP95
- 15SEP95 1
2 MAC AEVIEW SELF ASSESSMENT ACTION PLAN C 070-0020 16SEP95 17SEP95 2
2 AEVISE SELF ASSESSMT PLAN & SUBMIT MAC APPA0 VAL 0 070-0025 10SEP95 10SEP95 1
2 MRC APPA0VE SELF ASSESSMENT ACTION PLAN CORRECTIVE ACTION (080) iO80-0005 14AUG95 11SEP95 29 3
KVELOP CORRECTIVE ACTION ACTION PLAN 0 080-0010 12SEP95 11SEP95 0
3 SUBMIT CORRECTIVE ACTION ACTION PLAN L
I 0080-0015 14SEP95 14SEP95 1
3 MRC REVIEW CORRECTIVE ACTION ACTION PLAN C 080-0020 15SEP95 16SEP95 2
3 AEVISE COAR ACTION PLAN & SUBMIT MAC APPA0 VAL 0 080-0025 17sEP95 17SEP95 1
3 MAC APPROVE COR'ECTIVE ACTION ACTION PLAN
,h'
- $ [E' **"
kUBLICSERVICEELECTRI[GGAS
.,'*""'"'"'"cnm,,,,,,,,,1 h
m, ProjectFinish14JUN96 SALEM RESTART PLAN RESTART ACTION PLAN SCHEDULES (c) Pelaavera Systees. Inc.
c-v rwstvs e's\\a2sor saa r
EARLY EARLY ORIG TOTL 1995 START FINISH DUR FLT AUG l
SEP l
OCT EQUIPMENT RELIABILITY (090) 1090-0005 14AUG95 1SEP95 19 8
DEVELOP EQUIPMENT E LIABILIIY ACTION PLAN 0 090-0010 2SEP95 ISEP95 0
8 SUBMIT EQUIPMENT RELIABILITY ACTION PLAN TO MRC 0 090-0015 6SEP95 6SEP95 1
8 MRC REviEM EQUIPMEHi ELIABILITY ACTION PLAN 0 090-0020 7SEP95 BSEP95 2
O REVISE RELIABLE MAINT PLAN C SU8MIT MRC APPROVAL 0090-0025 9SEP95 95EP95 1
11 MRC APPROVE NLIABLE MAINTENANCE ACTION PLAN TRAINING (100)
'100-0005 14AUG95 SSEP95 23 9
3EVELOP TRAINir4G ELI ABILITY ACTION PLAN 0 100-0010 6SEP95 5SEP95 0
9 SUBMIT IRAINING RELIABILITY ACTION PLAN TO MRC 0100-00*5 8SEP95 8SEP95 1
9 MRC E VI$M TRAINING RELIABILITY ACTION PLAN O i00-0020 95EP95 10SEP95 2
9 EvlSE TRAINING PLAN C SUBMIT FOR MRC AoPROVAL 0100-0025 11SEP95 11SEP95 1
9 MRC APPROVE TRAINING ACTION PLAN l star sren 3 es 3 Plot Date 25AUG95 SALEM AESTART PLAN
_s utsvit[ earnerar cates I PUBLIC SERVICE ELECTRIC S GAS t
Data Date 20UL95 Cntua k t mer
- oat, n,,is,on cn n,a uccom'
_' WO** """"
SALEM RESTART PLAN
%*M!!!%inUSA o"
htdfART ACTION PLAN SCHEDULES (c) Primavera Systems, Inc c-V Nstw ors \\erso; oo 3 1
EARLY EARLY ORIG TOTL 1995 1996 START FINISH DUR FLT AUG l SEP l
OCT l
NOV l
DEC JAN I
FEB LICENSING PLAN (110) n110-1000 24 M 95 3SEP95 d2 0
SUPPORI UNIT 1 SYSTEM K ADINESS REVIEWS 1110-3G00 24JUL95 8SEP95 47 3
IDENTIFY LICENSING RELATED INITI ATIVES i
i110-3035 24AUG95 11SEP95 19 8
DEVELOP ACIION PLAN INTEGRATION MATRIX 0110-3040 12SEP95 12SEP95 1
8 REVIEW ACTION PLAN INTEGRATION MATRIX tf!TH SMRG i
1110-3005 20AUG95 14SEP95 18 3
MAC REVIEW ACTION PLANS & SERT RECOMMENDATIONS 0 110-1010 18SEP95 17SEP95 0
10 COMPLETE SCREENING U1 RESTART LICENSING ISSUES s110-3010
=
14SEP95 27SEP95 14 0
MIGS W11N SAP DN ACTION PLANS & CAL ITEMS 1.2.3 28SFP95 28SEP95 1
0 W
SAP - DISCUSS & CLOSE (IF POSS) CAL 1-3 hMPORTUNIT2 SYSTEM A0 JESS REVIEWS 21AUG95 10CT95 42 0
120CT95
!?OCT95 1
0 MTG (IF EQUIREO) TO CLOSE OUT CAL 1-3 0 110-3020 200CT95 190CT95 0
0 COMPLETE DOCKETING SUBMITTALS FOR CAL ITEMS 1-3 0 110-3030 270CT95 260CT95 0
8 REGION 1 AGREEMENT ON CAL ITEMS 1.2.&3 0 110-2010 310CT95 300CT95 0
0 COMPLETE SCREENING U2 RESTART LICENSING ISSUES
'110-4000
' REP LICENSING SUBMITTALS IN SUPPORT OF RESTART P
8 270CT95 70EC95 42 8
0 110-4005 169EC95 -
150EC95 0
182 UNIT 1 OUTAGE / RESTART WORK COMPLETE & 00CUMENTEC 0 110-4010 16DEC95 150EC95 0
182 FINAL UNIT 1 WALKDOWPG COMPLETE h.~A ChALREADINESSREVIEW 100EC95 230EC95 14 20 i
s110-4020 180EC95 300EC95 13 0
SVP-NO & CN0 APPROVAL TO RESTART 0110-4025 300EC95 30dEC95 1
29 SALEM ASSESSMENT PANEL UNIT 1 RESTARI MEETING U1 READINESS ASSk M hEAM 1 SPECTION
~
(RATIl 3JAN%
16JAN96 14 29 RESOLVE RATI ISSISS/SUBMI M k I J IIFICATIOh 17JAN%
24JAN96 8
29 D110-4036 25JAN96 25JAN96 1
0 PUBLIC EXIT hCCilNG RATI/ SAP /Sr NRC MANAGEMENT NRC REVIEW & APPROVE UNIT 1 T'O ENTER N00E 2 26JAN56 2FE896 8
28 ft.rt l $${}$ @
LBLIC SERVICE ELECTRI[ G bS d,'"m" "'" cn,u,a om, Project Unish HM66 Om meenm ety SALEM RESTART PLAN LICENSING RESTART PLAN
~
~ ~ ~ -
(c) Primavers Systecs. Inc e vrwst\\ptots\\sases oot 9
EARLY EARLY ORIG TOTL 1995
~
1996 START FINISH DUR FLT AUGl SEP l OCT l NOV l OEC JAN l FEB l MAR l APR l HAY l JUN UNIT 1 RESTART PLAN
+ tQ12 21AUG95 20AUG95 0
0 UNII.1 INITIAL 45 KEY SYSTEM WALK DOWNS COMPLETE 1000 24JUL95 3SEP95 42 0
J1 WOOK 8ACKLOG REVIEWED G SCREENED _FOR RESTART 1010 24JUL95 3SEP95 42 0
INIllAL UNIT 1 SYSTEM REVIEWS
+1011 4SEP95 3SEP95 0
0 AuL U1 SYSTEMS SCREENED FOR RESTART WORK SCOPE M 1100 24JUL95 175EP95 56 0
MBC REVIEW G ESTABLISH UNIT 1 SCOPE
+ 1101 18SEP95 175EP95 0
0 MRC FREEZE UNIT 1 OUTAGE / ESTART SCOPE
+1013 18N0v95 17NOV95 0
0 ALL U1 SYSTEMS EVALUATED FOR RESTART READINESS JNb 1 CORE OFFLOADED 5AUG95 24NOV95 112 0
PERFORM & DOCUMENI UNIT 1.0UIAGE RESI ARI WOh 24JUL95 150EC95 145 0
18N0v95 150EC95 28 0
UN N
46 KEY SYSTEM READINESS WALKDOWNS 30AUG95 230EC95 116 0
INULPENDENI_ HEADINESS ASSESSMENI UNil 1 0 NUU f 1 OPERATIONAL READINESS REVIEWS 100EC95 230EC95 14 0
1102 18SEP95 200EC95 102 0
MHC CONIROL UNil 1 EMERGENI WORK SCOPE 17NOV95 280EC95 42 0
MAC ASSESS UNI 1 RESTART REAOINESS M 1750 180EC95.
300EC95 13 0
VP-NO REVIEW UNIT 1 READINESS & APPRO)E REST ART
+ 1705 310EC95 300EC95 0
0 N01IFY NRC OF U1 READINESS & MODE 4 ENTRY W1 AIUP TO NOT/NOP & PRECRIT STARTUP TESTS 310EC95 13JAN96 14 28 14JAN96 2FE896 20 28 U
SHUTDOWN TESTING CORRECTIVE MAINT C1900 3FE8 %
2FEB96 0
28 UNIT 1 ENTER MODE 2 FOR STARTUP i
11910 3FE8 %
3 MAR 96 30 28 UNIT 1 RX STARTUP PHYSICS TEST & power ASCENSION
+ 1999 1ADR96 31 MAR 96 0
0 UNII 1 AT 100) POWER P
25AUG95 SN 5"'t o.lo.t Date i action.eI earners, ostes PUBLIC SERVICE ELECTRIC & GAS t-SALEN UN!! 1 AM) UNIT 2 FESTARI PL AN t o te muut9s m uc
=u ur o,t, ne, m on cnym acoro,ea U5 O ""'"'
d M N Ei Ori U N E o
SALEM RESTART PLAN UNIT 1 S UNIT 2 OUTAGE WORK ft) Primavera Systems. Inc r-V I*f 5T\\M G15\\9N 001
~
d
EARLY EARLY ORIG TOTL 1995 1996 START FINISH DUR FLT AUGl SEP l OCT l NOV l OEC JAN l FEB l MAR l APR l MAY l JUN UNIT 2 RESTART PLAN 18SEP95 17SEP95 0
0 4
INITIAL 46 KEY SYSTEM WALK DOWNS CDi'N.ETE 12221 24JUL95 10CT95 70 12 COMPLE.lE UNIT 2 FUEL POOL RERACK PROJECT m R000 21AUG95 10CT95 42 0
02 WOHK t3ACKL0u REVIEWED & SCREENED FOR RESTART 21AUG95 10CT95 42 0
TEMS REVIEWS
+ 2011 20CT95 10CT95 0
0 Alt '82 SYSTEMS SCREENED FOR RESTART WORK SCOPE 4SEP95 150CT95 42 0
LISH UNIT 2 SCOPE
+ 2101 160CT95 150CT95 0
0 MRC FREEZE UNIT 2 OUTAGE RESTART SCOPE I
m2220 70CT95 16FEB96 133 12 UNIT 2 CORE OFFLOADED 200CT95 1 MAR 9' 126 12 ORM & DOCUMENT UNIT 2 OUT AGE RESTART ORK i
12030 3rE896 1 MAR 96 28 12 UNIT 2 FINAL 4G KEY SYSTEM READINESS WALKDOWNS i
'2115.
2 PAR %
15HAR9E 14 12 CONOUCT U2 OPERATIONAL READINESS REVIEWS s2600 SOEC95 21 MAR 96 108 12 INDEPENDENT READINESS ASSESSMENT - UNIT 2 160CT95 22 MAR 96 159 12 MAC CONTROL UNIT 2 EMEflGENT WORK SCOPE 10FE896 22 MAR 96 42 12 MRC ASSESS UNI
. RESTART READItESS VP-NO REVIEW N ADINESS E APPROVE RESTART 16 MAR 96, 28HAR96 13 12 NOTIFY NRC OF kb READINESS & WDE 4 ENTRY 29 MAR %
28 MAR 96 0
12 29 MAR %
11APR96 14 34 UNIT 2HEATUPTONWNO
'& PRECRIT STARTUP TESTS 1APR96 25APR96 25 12 NRC'RATI E UTION OF FINDINGS 26APR96 3MAY96 8
12 NRC A UNIT 2 RESTAm 02900 AMAY96 3 HAY 96 0
12 UNIT 2 ENTER MODE 2 FOR STARTUI 4MAY%
2JUN96 30 12 UNIT 2 RX STARTUP PHYSICS TEST & POWER AS NSI0r; 15JUN%
14JUN96 0
0 UNIT 2 AT
% P0wE0
' EM %"I@ ""
kUBLICSERVICEELECTRI[GdAS
" *"js ) *"
EdU EU:
NIE oate e a amono
- !:n M in Unla o ? 2 2==o-a SALEM RESTART PLAN UNIT 1 8 UNIT 2 OUTAGE WORK kl Primavera Systems. Inc.
c-vtwsrsptois\\s2 sos e's
AUG-07-1995 08:01 P.03 j
i r
MRC FiVe-Day Look-Ahead (4:00-7:00 PM - Salem GM's Conference Room unless otherwise noted) lUste
& M e" e T,T4 bid MWWi+ia"dtJiEd!PPuseiife'r : WEIMbt]
Friday, August 4 Diesel Generator System D.Kolasinski/M. Rencheck Turbine Bypass Systyn Craig Johnson /M. Rencheck,,
Monday, August 7 Outage DCPs (SG01 turbine Ashok Moud ill & Project 8
runback, HEBA/MEBA, Managers Feed Ring &J-tube Mods,-
i Non-Safety 14 AWG Cable, i
and 10 Others)
Operator Workarounds JeffBeattie 13KV System Vijay Bhatia/M.Rencheck System Readiness Review TBD Tuesday, August 8 Configuration Walkdown George Englert Planning DEF ReviewPlanning Craig Lambert ControlRoom Annun/Indic.
Len Rajkowski System Read
- mess Review TBD F
System P=Aness Review TBD Wednesday, August 9 Unit 2 Turbine Rotors Bill Schultz Appendix "R" Issues Bill McDevitt/M.Bursztein e
System Readiness Review TBD System Readine,,s,,s Review TBD Thurssday, August 10 Mech Maint ATS Items Mike Metcalf System Readiness Review TBD System F**dinas Review TBD Friday, August 11 RMS Is!ues John Cicconi System Readiness Review TBD
. System Readiness Review TBD r
8/4/95 3:09 M 4 f
,,.mw:
a.
,.,,a....,,.. -
.,s.
..-as.as-.~mw
==
- m.. -,
--ns-a,-.s.,-
sr ume,-...2
.me.__-
-+ma s
.-s p-_s r.n. r _ mu. z e
.a - mn a-a a sa
,n o maa m _
i 4
1 0
4 i
5 4
i 4i I
1 i
i i
a i
l 1
t 4
1 1
4 h
' c+fES
{
i
. ir s
D
{
'ts 1
h e
f e
r i
s d
1 a
4 1
4 i
i h
i 4
1
-.. --s-
+- -
SLN! tsY:
8-8-85[4:58PM; PSE&G LIC & RECr.
610 337 5348:* 2/14
-o.
i
\\
l l
l l
l PUBLIC SERVICE ELECTRIC AND GAS COMPANY ORGANIZATION CHARTS AND BIOGRAPHIES AUGUST 8,1995 REVISED l
l l)'
- ~.
SENT BY:
8-8-95 : 4:59PM PSE&G LIC & REG 4 610 337 5349:# 3/14 4
S i
If}If i
g.
E 4
4 a
k E
$$ j I
ijI j la} !
4 i
8 8
s=
p d,g?
2-
}
J 3
1 1
E
9 NUCLEAR ENGINEERING & SUPPORT 1
a,,,3,,g:
l Semier Peament 7 NacierEngamanng i
Otc145) i Bat +
Aa- %-
i Semier m I
=
c'o '
secreamy TonyAmeo
~
j-BeuyKidd I,
c,,
Ad nad Re ew cup.
SB.
xi (ARC) R, -
vince1 % m i
$l I
I I
I
$l Manneer Manneer Manner Maanger l
Nuclear Esyneering Salan Beginemng NealeurPuel NuclearEnginseng HopeCamk 5-Taia 1 Manager I
e Proients OLC 149)
(RC 122)
Demon (RE 102)
(RC142) a,-
(RE 114)
=
hl Bill Sdadu(Actug)
BnmePaston ERiot R<==fdd Caig brahat j
Jam Claney l
SUPemasISIW SupuvisingISIBagmar SemorISIEnsimmr PrincipalEngmer Baden acost camol (RC 127) o c.=conne Bilt r=e=
tmuke CD ayth Pese
((
2!
..M E C'
I m
^ ^ ^~ ~
m
.9_,I NUCLEAM OPERATIONS 1
O mnt 2.s a'
Samar VinePrasadmit NuclearOperations (IUC959) j Imis senz SemorExecuane c>
t secretmy b
I -Open u
I i
i l
i i
ocomalManager Gener=1 Manner Dueanor Masseer Maasser m
1 58 ik,pe c,.ek opaw;ons salen opcations O peratsm a Sesw ees NuclearTauungCamer RahnhiktySarness
.. l t
x (RC 107)
(RC 069)
(IUC 113)
(IUC U6)
(R C 123) l l-MaAgauem mn Clay Waam Charly " - -- M RachardIYAnzm 3i j
JohnNichole g
Manager Manascr Welser Sommity Aanirustratar Manager l
C ',
D%j P.7A;;
La &Maamals Meenger Planning & Fi==nessi Protect-
O
& RadiologicalSupport Managanent (R C 115)
Control
&InstnHaan (R C 133)
(R C 118)
(IUC 135)
(RC148)
Tosn DiGaiseppi Charbe Smith DenRamocic I4retta Pennington Billher j
I I
I Aa~
Aamanstrative I
m g
Coordmatar Suppport o
O BdnaDue TracyHeans Ginny haunrup 8
Kelly M*=
si
~a W
p
,m,h.
m m
k
.T BUStheSS SUPPORT Chart 4.e si:
hPasidet NudentW Support k Hagan SeunctF~ --- -
8"7 M Hrasson cm' 1
1
?.
w>
1 I
Duectar Dumear Manager Meda:alDimsar M aar s,
- i. %, *
- arr.
-sr se m)
- s. -
{,
Finanenal Connel (R C 141)
(RJC M5) 3; (RE M2) o 2-Steve Cohen BobiwrneeUi Boboehnt RenMadt Imo Krajeenka m,
c-o i
'? '
6I C I G !
c,
4 I' o.
- i Rl r!
it
w:
QUAUTY ASSURANL,si/ NUCLEAR SAFETY REMEW
.f wi charts.e T
Duecear hQuahty Aa-r==rw/
Nudear SeistyRewiour SC293)
M"'"I""""
i t
Executive Secretary i
I I
I l
]
4 Manspr Mooneer Menspr Manage
$i NucherSafetyRmew Quaisy A========*
EmployeeCe NacisarUneming (RC 143)
(Hape Creek)
(IUC 226)
& Reguleaa ca i 2[
(RC292) 8 (R E 121)
Bruce Hall j
i -Open Jack Cany l
Frank Thr=nerm i
Manager Manser WProjects t
Conectiw Amon &
QuahayAssesmusst y;
Quakey Semons
@)
r$ !
n '
(RE29W289)
(IUC191) r-5 ':
Jaba Mornson j
D a msTauber D.Fr m=as i
- i t
t I
3!
e CJ I
~ !
Oe:
E !
Ca=resay Mgement WT A
r
HUMAN RESOURCES 8 ADMINISTRATION - RfC 168 c= ;
Chart 6A -
Duector t
NuclearHuman Renamoan l
A AA=ici aranon (RE166)
Chuck L4===
i I
Enscutave Seonsary c.x,
Dana Bussey c.r L I
I I
l l
l EE Emplejee Rdaba/
Adr==i*stive IR PImaning &
PrincipalNncker
! Qualnyh ph ca IneserialRdations Coonhastar Dndar"'""'
C h
gI Manager (RC166)
Manager
%*aar (RC134)
(RC 166) 2'
=
(R E 166)
(R E 166)
(RC166)
E j
c$
$l rT3 t-Telephone aw-e La==y a
sis."
l
[ no asei.ry WAPPO r ;l
~
s A*i-i*atiaa rx Melmeie DMarzio Ginny Smidnel Lied = Vreeland support CasoIF#
i gg i
comu.ciar sernces Pm-arR ans, v
imaw.ad K.e,, P.c-Unda Rathbane AnfyDayd Damashaua C-,
w I
h yo,a,,,a TrishPe&M U
3RIEEy ^ ' ' ' -
j FraskMustion 9%
e.
Facilities Wan===ar forOperunans e,
J-iSasth 3
KatyImch
}
9 c w a a.1 s vie i,
s ei a
KathyLTapr
%rt Time cn2!
A
- W i
SENI BY:
8-8-95 : 5:01PM :
PSE&G LIC & REG-.
610 337 5349:# 9/14 4
O PSI 4G Nuclear Business Unit Louis F. Storz f
f SeniorVice President-f-
i Nuclear Operations l
Louis F. Storz was named senior vice president-l 4
i nuclear operations in July 1995. He has overall responsibility for all nuclear operations of Salem j
and Hope Creek Generating Stations.
l f
'}
Prior tojoining PSE&G Storz served as vice president-nuc! car generation at Niagara Mohawk in New York. He was also general manager at Davis Besse Generating Station, and q
i was promoted to vice president-nuclear of i
Toledo Edison Company, which operates Davis
?
Besse. Storz also served as assistant plant man-ager at Louisiana Power & Light Company's Waterford Generating Station and assistant plant manager for operations at South Carolina Power & Light Company's V.C. Summer Generating Station. He has held a number of technical and managerial positions including superintendent of operations at the Point Beach Nuclear Generating Station operated by Wisconsin Electric Power Company, Storz participated in INPO's (Institute of Nuclear Power Operations) Utility Loan Program and has held engineering positions with Babcock and Wilcox Corporation and PPG Industries. He served in the United States Navy's nuclear submarine program from 1960-67.
l Storz holds a bachelor of science degree in mechanical engineering from Purdue University, t
l
}
}
h m see i
h 1
,SENI BY:
8-8-05 ; 5:03FM.
PSE&G Llc & REG-610 337 5340:#11/14 l
O PSidG t
Nuclear Business Unit Elbert C. Simpson Senior Vice President-j NuclearEngineering
. n J, 1
1 j
Elbert C. Simpson was named senior vice presi-dent-nuclear engineering in June 1995. He j
oversees all engineering activities for Salem and l
l j
Hope Creek Stations and the Nuclear Business i
Unit.
O 1
S.impson was v. ice president-nuclear support for 1
wwn j
Arizona Public Service Company, which oper-T l
ates the three-unit Palo Verde Nuclear Generat-ing Station, prior to joining PSE&O. He over.
saw nuclear engineering, construction and support in this position. Simpson also held a number of managerial positions with Florida t'
t, Power Corporation, includng director-ruclear operations engineering and projects, director-nuclear operations site sup-port, and director - nuclear operations engineering and licensing.
i j
Simpson holds bachelor of science degrees in electrical engineering and nuclear engineering from University of Florida.
I i
I l
l l
i i
i i
i m ses I
l
.SEM BY:
8-8-05 ; 5:02PM ;
PSE&G LIC & REcc 610 337 5348:#10/14 O psi 4G
)
Nuclear Business Unit Clay C. Warren
[IF
' ~ 79 General Manager-Salem p1 1
,s y
Generating Station f
ty.
Clay C, Warren was named General Manager-l Y
Salem Operations in July 1995. He has direct l
responsibility for the operation of Salem Gener-j:
.i j
ating Station.
3
($
{
j Warren previously served as General Plant ja Manager of Carolina Light and Power's Q t'
/
4% j4 2,.;-
)
Bmnswick Nuckv Plant where he was respon-y 9-Q '
sible for all aspects of plant operations, mainte-
.j.
6?
1 f
9g l
nance and outage management. He also served 4'
- f j
'[' '[j.
j as maintenance manager at Arkansas Nuclear e
One, and consulting deputy outage manager at Boston Edison Company's Pilgrim Station. Prior to that position, Warren spent five years as a senior inspector for the Nuclear Regulatory Commission at three different nuclear plants. He began his career in the nuclear industry in the United States Nuclear Navy. When he left in 1979, he was the Leading Petty Officer in the Reactor Controls Division.
f He holds a bachelors degree in natural science from Louisiana State University and received i
Senior Reactor Operation License training in 1985.
sv tos4 i
g e
1 I
O PSMG Nuclear Business Unit Jeffrey A. Benjamin Directors-Quality Assessment and Nuclear Safety Review l
4,,
t -.
Jeffrey A. Bordamin was named director-
$ ' $ + N;,-
quality anessment and nuclear safety review in f
December 1994. As director, Benjamin is re-
-t sponsible for overall management of quality 1,y".. '
assurance and nuclear safety review programs at j
Salem Units 1 and 2, Hope Creek Station and all y,/
j supporting departments. He also serves as
'(
I',
chainnan of the Nuclear Review Board and g
t oversees licensing and regulation.
~
Benjamin had been manager of quality assess-y L
ment for the Washington Power Supply System in Richland, Washington. While at WNP-2, Benjamin successfully completed the BWR Man-j agement Certification program.
{
Prior to assuming his position at the ' ?SS, Benjamin served as quality control manager, j
quality audit supervisor and nuclear safety engineer at the Trojan Nuclear Plant in Oregon. In i
I addition, he worked as a reactor engineer at the Hanford Nuclear Reservation.
i Benjamin received his bachelor of science degree with honors in nuclear engineering from Oregon State University and is a candidate for a master's degree in nuclear engineering from t same institution.
i l
i 2
3 i
- --'~ ~ ~
' ~ '"~
~
l SBT BY:
8-8-95 ; 5:04PM ;
PSE&G LIC & REG-6t0 337 5349:#13/14 4
i; i
t PSMG j
Nuclear Business Unit 1
t l
Joseph J. Hagan 1'
Vice President-Nuclear
.L<
Business Support j
l Joseph J. Hagan was named vice president of
- Q
.!J j
nuclear business support in July 1995. He has jT'
~t?
overall responsibility for the follovang support functions: budget and strategic planning, infor-mation systems, external affairs, medical and in-
,.m.
processing.
Haganjoined PSE&G in 1970 and has held a
{
number of supervisory and senior management
[33 Y.I
' ]
{I((
-Q q
j positions, including vice president of nuclear
- k j
operations, general manager of Hope Creek Sg""
operations and general manager of Salem j
operations, maintenance manager and station planning manager at Hope Creek Generating Station, and senior maintenance supervisor at Salem Generating Station. Prior tojoining the Nuclear Business Unit, he was a supervisor at Mercer Generating Station and spent several years j
in the Electric Transmission and Distribution Department of PSE&G.
I
{
Hagan holds a bachelor of science degree in electrical engineering and a master ofscience degre in engineering management from Drexel University. He has completed the program for Manag ment Development at the Harvard Business School, the Advanced Management Course at i
Rutgers University and was licensed by the Nuclear Regulatory Commission as a senior reactor j
operator for Hope Creek Generating Station. In addition, he holds a boiling water ccrtification from General Physics.
J j
Hagan serves as campaign chairman for the Salem County March of Dimes WalkAmerica.
1 i
l I
I
~
s j
l pa ay:
u-u-35 : 5:05PM :
PSE&G LIC & REG-610 337 5349:#14/14 1
l f' '
i i
O PSEG Nuclear Business Unit
{
Leon R. Eliason E.
Chief Nuclear Officer &
T 5:
.p President-Nuclear Business Unit
~
l M,
- m
- r...
m...
a
- a. :n i
Leon R. Eliason wal named chief nuclear ofUcer
- .== :::
and president of the Nuclear Business Unit in C
W.
r~~".
October 1994. He is responsible fo'r all operational
,.-a; C
j and support activities for the two-unit Salem Gener-
~
l ating Station and Hope Creek Generating Station.
z
- A._
{
As CNO and presideat, Eliason reports to Public g
Service Enterprise Group CEO E. James Ferland.
s j
i Eliason came to PSE&G's Nuclear Business Unit V
{
after serving as president--generation for Northem States Power (NSP) in Minnesota, where he oversaw j
the operation of fossil and nuclear power generating plants and related activities. He previously served at NSP as vice president-nuclear generation.
l general manager-nuclent plants, Monticello plant manager and as a radiation protection engineer.
He has been involved in the nuclear industry for more than 25 years.
Eliason holds a bachelor of science degree in mechanical engineering from the Snuth Dakota School of Mines and Technology, and is a graduate of the University of Minnesota Management Institute.
He is currently active in the following professional groups:
Association of Edison Electric Illuminating Companies' Power Generation Committec
]
Institute of Nuclear Power Operations' National Nuclear Accrediting Board 1
I He was chairman of the New York Power Authority Advisory Group, and was a member of the j
following industry organizations:
j e Washington Public Power Supply Corporate Safety Review Board
{
e NRG Energy, Inc, e American Nuclear Society Eliason also served on the Board of Directors of the St. Croix (Minn.) Catholic Consolidated j
Schools, and is a member of the Stillwater (Minn.) Knights of Columbus and the Metropolitan
]
Economic Development Board.
l, I
,sw 1Q44 a
.-... - -.~
- - - - - - - _ _ -. -.. -. _ -. - -..... ~.. _. -.. -.. - -. -...
i i
k h
i b
b 4,
4 4
i j
l l
d e
l
^
~ ^'~
~ ~ ~
rme I
s.
We 5ENT BY:
7-22-03. 8:36AM.
PSE&G LIC & REG-610 337 5324:s 2/ 3 l
Pubbe Seiwce th:dm.auf Gas twtur I
Joseph J. Hagen Pubbe Semcc Electric aw Cao Company P o enn 236. Hancocks Dnege. HJ 08038 600 339-1200 v c e w
.en,e.ac co eve JUL 221995 LR-N95024 k
United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn:
Mr. T. T. Martin, Administrator - Region I-MANAGEMENT OBSERVATION GROUP
$ALEM GENERATING STATION UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 By letter dated May 13, 1994, Public Service Electric & Gas (PSE&G) committed to provide augmented oversight of plant activities prior to restart of Salem Unit 1 following the April 7, 1994, reactor trip and safety injections.
To meet this commitment a Management Observation Group (MOG) was formed.
By letter dated May 14, 1994, the NRC accepted this commitment as well as our plans to restart Salem Unit No. 1.
The purpose of this letter is to notify you that PSE&G is climinating the MOG commitment.
However, we are not eliminating the MOG function.
PSE&G plans to maintain a level of MOG coverage commensurate with plant conditions so that adequate oversight and feedback to Salem management will continue.
Furthermore, we are continuing to take actions necoccary to improve management oversight effectiveness as part of our performance improvement plan.
Transmittal of this letter satisfies our commitment to notify you of any " relaxation" in MOG activities.
Thia requirement was documented in your May 14, 1994 letter.
Also, these changes were discucced with Mr. John White of your staff on July 20, 1995.
4 I
i I
i l
l I
I
\\
l l
1
/
l kb b i S b OC E'i h
I 1
SENT BY:
7-22-03 8:37AM -
PSESG Llc & REG-610 337 5321:" 3/ 3
, h/.
i l
\\
j, nocument control Desk JUL 221995 LR-N95024 should you have any questions, we will be pleased to disctins them with you.
Sincerely, 6
^^
t C
Mr. T. T. Martin, Administrator - Region I I
U.
S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 i
Mr. L.
N. olehan, Licensing Project Manager - Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr.
C. Marshall (309)
USNRC Senior Resident Inspector Mr. K. Tosch, Manager IV NJ Department of Environmental Protection Division of Environmental Quality i
Bureau of Nuclear Engineering CN 415 Trenton, NJ 08G25 i
1 l
i l
4