ML20115A814

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Marked-up Draft Summary of NRC Caseload Forecast Panel 840222-24 Meeting W/Util & Site Tour.List of Attendees, Meeting Agenda & Draft Tm Novak Ltr Encl
ML20115A814
Person / Time
Site: 05000000, Limerick
Issue date: 04/11/1984
From: Harrison G
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
Shared Package
ML082170543 List: ... further results
References
FOIA-84-367 NUDOCS 8504160131
Download: ML20115A814 (23)


Text

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UNITED STATES 8.

NUCLEAR REGULATORY COMMISSION f,. ,

WASHINGTON. D. C. 20555 gl

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A APPLICANT:

Philadelphia Electric Company (PECO) yT

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FACILITY:

Limerick Generating Station

SUBJECT:

SUMMARY

OF CASELOAD FORECAST PANEL (CFP) MEETINGS AND FACILITY TOUR AT LIMERICK APR7LW4WWfytB885 FagdARV 22-M 198+

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% the NRC Caseload orecast Panel (CFP), consistin l

2 of William Lovelace (RM/DMI),. -=-*-m-tis (LicensingProjectmanager)andk Suresh Chaudhary (Sr. Resident Inspector), met with the applicant and oured Ak the Limerick facility and site. The purpose of these meetings and tour was fe ec[cc

~1e review construction progress,and cc'- ' htQfor the purpose of assisting T i C'f-l the NRC staff in estimating its resource needs for licensing activities for rul/kfi Limerick. The visit was organized in three parts:

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On a meeting was held with the applican,t at the MM MW f h g p r--

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,_to review design and engineering, procurement, and construction progress on. Limerick.

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On a tour of the Limerick facility and site was made to observe the status of construction. The CFP also held brief discussions with the applicant epufg$$23F concerning questions raised during the meeting

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and tour.

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a second meeting was held with the app.licant at the 'h, g

r#casempnamer to discuss questionsiraised during the Fe.bnej/ "

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AptMfas meeting and delusisimiIhtour. At the conclusion of this meeting, i

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the CFP stated that the infomation provided by the applicant and chstW WS lY from the facility tour would be evaluated by the NRC ' staff. "'^ :pp',innt-v2e mr+har informed that if the evaltratinn ind h t^d : diffu u..cc-l

f me: 0 - than cir mnnths between the CFP estimated < nn-Mhnla+4^'

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applicent':, : m::th; roul-d-be-. eEbied Limien r R6 -

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""nanement-and-PECO m:nagement. -

If Meeting and Facility Tour Details LM No W 14 f 4 4-2t9 1961 498SAat the

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u The Caseload Forecast Panel (CFP) met with the applicant at the Ebona2terf4Mtedy

%, M'immuac^;;;&H A list of attendees at the meetings through Friday, Ap+t*+M5[v 2Vy is included as Attachment 1. p_

A copy of the meetino acenda is included as AttachmentI x 8504160131 840606 4

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he applicant stated e Limerick Generating Station Unit I was complete t the end ofj h g my. A list of major milestones and recent schedule accomplishments, as p" resented by the applicant, are included as Attachments 3 and 4.,

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Licensing support c.

Issue of remaining Design Change Packages f

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Closeout of outstanding documentation i

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Field support, such as:

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- Final assessment of blockwalls for loa s due field-routed commodities, as required

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- Structu rity Test Support f.

Start up support, such as:

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- Resolution of startup problems Assistance with procedure preparation J

Review approval of test results 1

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.a Procurement of large piping is complet8.

Procurement of small p i p i n g,i s. c o m p l,e, t e.

  • Large hangers and anchors are 99+% complete.

A detailed review of pipe hangers will be made in Agenda Item 5.

  • Engineered valves, both large and small, are grouped together for reporting purpose and are complete with the exception of 35 pressure relief valves which are being re-worked by Crosby Valve with a current May 1984 delivery l

schedule.

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Significant Activities

  • Equipment Oualification - The last technical services contract for equipment qualification of saall electrical N

components was issued during January.

The contractors final report is scheduled for submittal by March 30, 1984.

  • The Field continues to identify additional Limitorque valve operator component failures that require replacement.

A continuing effort is in progress to expedite immediate action upon field purchase orders issued to Limitorque, j

including weekly visits by field expediters to the Limitorque factory.

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j WP phe Limerick Spare P Program is being implemented on a is pdrchase order by purchase. order basis.

The end result of the program will be a computerized listing of parts for each piece of equipment in the~ plant. A sub-routine of the Spare Parts Program is the determination of which spare parts are safety-related and the development of a procure-ment specificati'on for each safety-related part, f The Spare Parts Program has been staffed since August, 1979.

The PECo program is supplemented by a Bechtel group which reviews Construction experience, Startup experience and parts lists from the Spare Parts group.

They use the Bechtel Procurement process to obtain items which would be considered "high use" or "early failure".

Examples include l

gaskets, o-rings, diaphrams and filter elements.

In add-t ition, the availability of Unit 2 equipment as potential spares for Unit 1 provides a measure of insurance for items that are not stock items and may have a long lead time.

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Thursday, The CFP toured the Limerick site on Thursday to observe the status of construction.

Among the areas observed were the containment building (including the drywell)l

...JA the turbine building, the contro

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=ad ^*1 room, the radwaste building, the diesel generator building and the refueling area.

A brief meeting was held to discuss additional information necessary for the NRC staff to make its evaluation of the limerick Unit i fuel load date, Friday,f"r" t Tts1934k G O V M n %}r;:,$% W w w

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^t gy A number of ' concerns were discussed in further detail on Friday. These concerns were in the following areas:

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Spare Parts

'II. Stress Reconciliation /N-5 l

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Software Closeout

. IV. GE Design Changes i

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Room Turnover VI.

DCP's and Preop Testing l

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Security Staffing m

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,% *AL Control Room Penetration Seals Pipe Whip Restraints l

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' provided by the applicant would be reviewed and the applicant's projected fuel-j load date would be evaluated. 4f dit ccelestie6 indicated a difference i-

_,/ kr Tstimai.co fuei luau cates vi mure i.h o n six me60i> audii.iunal diw ussions oetween

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___3, Pr'oject Manager Licensing Branch No. 2

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Division of Licensing Attachments:

As stated cc w/ attachments:

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ATTENDANCE LIST NRC CASELOAD REVIEW LIMERICK INFORMATION CENTER FEBRUARY 22-24, 1984 Name

' Affiliation Greg Harrison NRC W. H. Lovelace NRC J. T. Wiggins NRC S. K. Chaudhary NRC J. S. Kemper PECO J. P. Law PEC0 J. M. Corcoran PECO L. E. Pyrih PEC0 J. R. Coughlin Bechtel Joseph T. Smugeresky PEC0 J. J. Clarey PEC0 J. W. Spencer PEC0

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G. M. Leitch PEC0 K. Dickinson Bechtel

0. G. Brown Bechtel W. C. McDaniel Bechtel T. P. Gotzis PECO J. G. Weisheit PEC0 E. D. Patel Bechtel S. P. Mainai Dept. of Env. Resources R. D. Rawlings Bechtel J. B. Cotton PEC0 C. R. Endriss PECO P. J. Duca PEC0 R. A. Mulford PECO J. L. Collings Bechtel J. M. Anderson Bechtel V. S. Boyer PECO E. Firth PEC0 R. Stout Bechtel - PFQCE J. Gallagher PECO S. Daltroff PEC0 W. Wagner Bechtel P. Naugle PECO W. Shuff PEC0 J. Milito PECO i

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LIMERICK

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CASELOAD F0P.ECAST PANEL SITE Visli NEETING AGENDA Overview of project construction and preoperational testing schedule, 1.

including progress and major m'ilestones completed, current problems and any anticipated _ problem areas that may impact the current pro-jected fuel load date.

Detailed review and current status of design and engineering effort 2.

(by major disciplinel, including any potential problems that may arise from necessary rework..

Detailed review and current status of procurement activities, including 3.

valves, pipe, instruments, cable', major components, spare parts, etc.

Actual and proposed craft work force (by major craft), craft avail-4.

ability, productivity, potential labor negotiations and pro 61 ems.

Detailed review and current status of all large and small bore pipe 5.

hangers, restraints, snubbers, etc., including design, rework, pro-curement, fabrication, delivery and installation.

Detail.ed review of project schedule identi fying critical path items, 6.

near critical items, amount of float for various activities, the current critical path to fuel. loading',- methods of implementation of corrective action for any activities with negative float, and provisions for contingencies.

The estimated project percent complete as of January 31, 1984.

Detailed review and current status of bulk quantities, including 7.

curr'ent estimated quantities, quantities installed to date, quantities scheduled to date, current percent complete for each, actual versus forecast installation rates, in cubic yards /mo., linear feet /mo., or number /mo., and basis for figures.

(a)

Concrete (CY)

(b)

Process Pipe (LF)

- Large Bore Pipe (21/2" and larger)

- Small Bore Pipe (2" and smaller)

(c)

Yard Pipe (LF)

(d)

Large Bore Pipe Hangers, Restraints, Snubbers (ea)

(e)

Small Bore Pipe Hangers, Restraints (ea)

( f)

Cable Tray (LF) av.

2 (g)

Total Conduit"(LF)

(h)

Total ~ Exposed $etal. Conduit:{LF)

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Instrumenta tion.

- Plant Lighting, (j).. Terminations (ea)

- Power

- Control

- Security

- Instrumentation

- Plant Lighting (k)

Electrical Circuits (ea)

- Power

- Control i

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- Secu'rity (1)

Instrumentation (ea)

Detailed review and current status of pre, paration of preop and acceptance 8.

test procedures, integration of preop 'and acceptance ' test activities with construction schedule, system turnover schedule identi"fying each system and status, prbop and acceptance tests schedule identifying each test and status, current and proposed preop and acceptance tests program manpower.

.(a) Total number of procedures required for fuel load, (b)

Number of draft procedures not started, q

t (c)

Number of draft procedures being written.

i (d)

Number of procedures approved.

' 'I-(e)

Number of procedures in review.

( f)

Total number of preop and acceptance tests required for fuel i

load identifying each.

(g)

Number of preop and acceptance tests completed identifying each.

(h)

Number of preop and acceptance tests currently in progress identifying each and status.

(i)

Number of systems and/or subsystems turned over to start-up l

identi fying each.

(j)

Number of systems turned over to operations group identifying each and outstanding open items for each system.

(k)

Number'of retests expected, if any, identifying each and cause l

for retest.

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3-9.

Detailed discussion of potential schedular influence due to changes

. attributed to NUREG-0737 and other,recent licensing requirements.

'10. : Discussion of schedular ' impact, if any, regarding potential deficiencies

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l reported in accordance w'ith 10 CFR 50.55(e).

11. Overview of current construction and startup management organization showing interfaces between the two.
12. Detailed review and current status of design, engineering and construction effort including quantities, work-off rates and schedule for completion for:

(a) ATWS-3A Design Changes (b) Appendix R Design Implementation (c) NSSS Loads Adequacy Evaluation (d) High Energy Line Break (HELB)

(e) Moderate Energy Line Breaks (l1ELB)

(f) Downcorner Capping / Vacuum Breaker Valves (g) Reactor Coolant Pressure Boundary Leak Detection (h) Control Room Panel Modifications (1) Pipe Stress (as-built) analysis (j) N-Stamp Certification Program (k) Updating Drawings and Specifications to as-Built Condition

1) Environmental Qualification of-Safety-Related Equipment m) Seismic Qualification of Safety-Related Equipment,

n) Hanger Reconciliation Program

13. Detailed review of room / area turnover schedule and status.

14.

Projected requests for relief of incomplete items, systems, or test completions at the time of Unit I licensing, identifying each.

15. Review of open punca list items by category (hardware / paperwork) identifying each and work-off rate vs add on rate.
16. Review and status of Unit 2 Control Room panel modification work required to be completed prior to Unit 1 fuel load.
17. Status and schedule for Seismic II/I review.

(IEB 79-14) i l

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18. Detailed review and current. status of power accession testing procedures and operational procedures.

A.

Power ascension' test procedures including' safety-related and nonsafety-related.

1.

Numbers required 2.

Numbers not started 3.

Numbers in preparation and approval process 4.

Numbers approved B.

Operating procedures required for fuel loading; including station administrative, station operational, surveillance (e.g., technical specification), maintenance and emergency procedures.

1.

Numbers required 2.

Numbers not started 3.

Numbers in preparation and approval process 4.

Numbers approved

19. Detailed review and current status of permanent station and support staffing training and licensing.

Staffing for Unit 1 operation, including presently employed, projected a.

and authorized for each group reporting to the Vice President Nuclear (Reference FSAR Figure 13.1-2).

l b.

Staffing of Limerick (Unit 1) station organization including presently employed or contracted, projected, and authoirzed for each organizational. subgroup (Reference FSAR Figure 13.1-4).

Training program; outstanding training courses required prior to fuel c.

load; identifying job titles, numbers of personnel, and projected l

completion.

d.' Operator and senior operator licenses presently onsite, contracted, projected, and required for fuel loading.

20.

Site tour and observation of construction activities.

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CONSTRUCTIOt.' PROGRESS A. significant construction accomplishments since the last review meeting in April, 1983 include the following:

Scheduled Actual Turnover of 6 NSSS Systems in Support of the 5/15/83 to.

7/1/83 to Integrated Recirc Flush 7/13/83 8/17/83 Completed Suppression Pool for Fill 6/15/83 7/1/83 Completed RPV Internals for Initial Fill of RPV

.7/1/83 7/1/83 CRD Hydraulic Control System Complete 8/2/83 11/10/83 Diesel Generator System Turnover 8/15/83 1/24/84 RPV Code Hydro 9/17/83 8/27/83 Perkiomen Pipeline Completed and Hydrotested 11/4/83 10/7/83 Refueling Floor Negative Leak Rate Test 2/4/84 1/25/84 2/10/84 Generator Air Test Completed RPV Internals for CRD Vent and Stroke 2/15/84 10/17/83 i

B. Other construction accomplishments since the last review meeting include the I

following:

Substantially Completed Unit I Control Room Panel 12/83 Modifications (Remainder Coordinated with Gystem Preops) i New Fuel Storage Area Complete 11/83 Spent Fuel Rack Installation Complete 12/83 Completed ATWS III A Construction 1/84 f

ERFDS (Safety Parameter Display System) 98% Complete 1/84 Completed 224 of 307 Startup Subsystems 2/2'1/84 Refueling Floor Pools Completed and Hydrotested 2/84

. Completed 75% of Protected Area Boundary Fencing 2/84

g. The status of the following key construction activities is as follows:

Percent Complete Wire and Cable Pulling 97%

Connections 96%

Hydrostatic Testing 95%

Blue. Tag Releases 95%

Permanent Plant Security System 97%

HVAC Installation 98%

Subsystems submitted to Startup 71%

Thermal Insulation Installation 43%

Penetration Seal Installation 45%

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REV. 8 MILESTONE LIST Rev. 8 j'

Sched. Date g

Sched.

Actual A MILESTONES (Major)

-Complete Complete

Energization 04 Jul 82 04 Jul 82 A Integrated Recirc Flush 14 Aug 83 20 Aug 83 A RPV Code Hydro 17 Sep 83 27 Aug 83 A Loss of Air Test 09 May 84 ILRT 24 May 84 Loss o f AC Powe r 31 May 84 Cold Functionals 31 May 84 Fuel Load

.25 Jul 84 8, INTERMEDIATE MILESTONES (Minor)

Start Comple te Integra ted Condensate Flush 03 Feb 83 A 06 Mar 83 A Filling the Suppression Pool 06 Jul 83 A 06 Jul 83 A Full Flow Vibration Test 30 Sep 83 A 07 Oct 83 A Core Spray Orifice Sizing 21 Nov 83 A 04 Feb 84 A Steam Blows 23 Nov 83 A 12 Mar 84 Generator Air Test 07 Nov 83 A 03 Feb 84 A CRD Ve'n h & Stroke 21 Nov 83 A 28 Dec B3 A Core Spray Preop 14 Dec 83 A 30 Jan 84 EHR Preoo 04 Feb 84 A 12 Mar 84 Diesel Preop 17 Feb 84 03 Apr 84 Full Core Scrams 09 Mar 84 14 Mar 84 Condenser Vacuum Test 15 Mar 84 28 Apr 84 Electr ical Outage 15 Mar 84 28 Mar 84 Receive Fuel on Site 20 Mar 84 31 May 84 l

Ooe ra tiona l - Hydro 03 Aor 84 09 Aor 84 Control Room Isol Test 04 Aor 84 10 Apr 84 IHSI 10 Apr 84 24 Apr 84 Con ta inment Isol Test 16 Aor 84 07 May 84 RFP Turbine Runs 24 Apr 84 14 May 84 Receive Fuel on Floor 01 May 84 06 Jun 84 Security Operational Tests 02 May 84 12 Jun 84 Emergency Drills 25 Jul 84 25 Jul 84

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LIMERICK CENERATING STATION l'

UNIT I & COMMON BULK QUANTITY STATUS FE' FINAL TOTAL COMMODITY INSTALLATION ACCEPTANCE ACCEPTANCE SCOPE Concrete 100%

100%

100%

271,300 CY Large Pipe 99%

99%

99%

339,100 LF I

Large Pipe Hangers 99%

97%

93%

14,000 EA Small Pipe 99%

93%

91%

269,200 LF Small Pipe Hangers 98%

89%

85%

32,400 EA Instrument Tubing 99%

97%

96%

115,000 LF Instrument Devices 96%

96%

96%

7,100 EA Cable Tray 100%

100%

9,9%

48,900 LF Conduit 98%

97%

89%

387,000 LF i

Wire & Cable 97%

97%

97%

6,060,000 LF l

Connections 96%

96%

96%

188,400 EA l

Pipe Insulation (S/C) 43%

43%

28%

120,000 LF Penetration Seals (S/C) 45%

45%

43%

3,000 EA

SYSTEMS COMPLETION A revision to the Start-up Schedule (Rev. 8) was issued on 1/21/84.

Revision 8 requires the submittal of 307 subsystems by May 1984 in support of a July fuel load. The submittal dates were developed by adding the required testing durations to the estimated completion dates for each sub-system. AJ of 2/21/84, the current status per revision 8 is as follows:

To Date Status (2/21/84)

Sched Actual d

lasue Punchlists 283 293

+10 Complete Blue Tag Releases 256 251 (5) i Contruction Complete 226 241

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l Complete Testing / Submit 226 224 (2) l Turnover Package i

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SYSTEMS TO SUBMIT NUMBER OF PRE-OP/ ACCEPT TESTS

'.TEGORY OF SYSTEMS TO BE SUBMITTED (AS OF 2/21/84)

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Perkiomen 12 11 1

5.) Electrical (Lighting-Misc.)

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6.) NSSS 6

6 7.) Emergency Drill Systems 7

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Reactor Protection Systems 6

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Computers & Assoc.

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2 4 kI*) Primary Containment 4

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TBD 3 3-) Generator 1

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"STARTUP' PROGRESS

SUMMARY

(Basis - Rev. 8) 4 Complete 18 FEB 84 Sch'ed / Actual Total Plant Effort 71.0/61.7

" Blue Tag Testing

'87.0/81.6 78.5/72.0 Subsystem Turnover Submittals Initial Doerations, 71.0/66.1 Flushes and Energizations Startuo Work List 66.0/55.4 Workoff Test Procedure Review 94.0/88.0 Cycle Complete 33.5/20.8 Test Performance Test Reoort Review 19.4/ 9.1 STARTUP WORK LIST

SUMMARY

Total number of onen items = 4398 Approx number of open items last month = 5355 Total number of items removed = 1186 Total number of items added = 229 PECo ooen items = 1298 Construction open items = 1250 Resident Engineering open items = 229 Field Engineering open items = 568 G.E. open items = 192 OC open items = 663 Procurement items = 36 Unassigned items = 43

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PROCEDURES The current orocedure status in as follows:

Sched Act~Hiiil.

Preons Tasts identified 106/106 Procedure writing started 106/106 Procedure writing completed 106/100 SSE review started 106/99 SSE review completed 102/96 TRB-submittal comoleted 83/76 TRB approval como'leted 70/57 NRC submittal comoleted 70/55 NRC review comple'ted 41/42 Tasts aporoved 39/42 Tasts started 32/25 Tests comoleted 23/13 Rasults submitted to TRB 22/10 Rasults approved by TRB 11/1 Acceotance Tasts identified 40/40 SSE review started 34/32 SSE review completed 29/27 Tasts aooroved 29/27 Tasts started 22/19 Tasts completed 16/14 Rasults submitted 14 /9 Rasults aoproved 11/5 The following twelve (12) preop tests and.iiv e (5) acceptance tosts are in progress:

Tast Descriotion

% Cpt Test Description

% Cpt P6.1 Safeguard 440 MCC 75%

AS.1 Nonsf Ld Center 45%

P14.1 Rx Enci Cooling 5%

A12.1 Non-Sfgd 44 0 MCC 40%

P23.1 Diesel Gen Oil 5%

A84.1 Moist Sep/Drn 15%

P31.lB Pr imary Computer 40%

A88.1 250 VDC Power 90%

P41.1 Cooling Tower 75%

A92.1 Sealing Steam 80%

P44.1 Condensate 90%

P46.1 Extract Steam 50%

P49.1 RMR 25%

P51.1 Core Soray 60%

P55.1 Rod Hydraulic Supp)v 90%

P58.1 Reactor Prot.

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PS4.1 MG Sets /Rx Recirc 20%

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UNITED STATES NUCLEAR REGULATORY COMMISSION 7,

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Docket No. 50-352 x

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Mr. Edward G. Bauer, Jr.

Vice President & General Counsel

,1 T] b ct W Philadelphia Electric Company

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2301 Market Street Philadelphia, Pennsylvania 19101

Dear Mr. Bauer:

Subject:

Results of NRC Caseload Forecast Panel Meeting at the Limerick Generating Station, Unit 1 Members of the NRC staff participated in meetings with the Philadelphia Electric Company (PECo) and toured the Limerick Generating Station (LGS) site during the period of February 22-24, 1984. The purpose of these activities was to gather data to assist in developing an assessment of the schedule for completing construction, testing and other activities necessary to support issuance of an operating license and the loading of fuel for the LGS, Unit No. 1.

On the bases of the plant tour and the infortnation provided NRC staff by PEco in February 1984, the NRC staff believes th'at the PEWfuel, load date of August 1984 to be optimistic.

The NRC staff is aware that PECo management remains convinced of the feasibility of meeting the August'1984 date for Unit 1 fuel loading.

In sumary, the staff believes that there is significant evidence to suggest that construction related activities may be accomplished in the August 1984 time frame. However, the staff was not able to identify during the February 1984 visit a basis for believing that the extensive pre-operational and acceptance testing activities, and subsequent turnover of the systems to the operations group are likely to be completed and in place by August 1984. Accordingly, in order that we can better understand you basis for projecting a readiness for fuel loading in August 1984, including satisfactory completion of all preoperational testing systems important to safety, we plan to request a sinfor level management meeting. The.NRC project manager for NRC, Robert Martin will contact you in the near future to establish a mutually agreeable schedule and agenda for such a meeting.

Thomas M. Novak, Assistant Director for Licensing Division of Licensing

Enclosures:

As stated cc: w/ enclosures See next page w

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