ML20127M938

Forwards Util to NRC Indicating Anticipated Fuel Load Readiness Date for Plant Changed from June 1985 to Sept 1985,as Suppl to Silberg .Related Correspondence

ML20127M938
Person / Time
Site:	Perry
Issue date:	06/21/1985
From:	Woodhead C NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD)
To:	Bright G, Gleason J, Kline J Atomic Safety and Licensing Board Panel
References
CON-#385-625 OL, NUDOCS 8507010394
Download: ML20127M938 (6)

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4 UNITED STATES

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C {kg NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555

...., + June 21, 1985 00CKETED USNRC

'85 JUN 28 Pi37 James P. Gleason, Chairman Dr. Jerry R. Kline OFFICE OF SECRtTMv Administrative Judge Administrative Judge 00CXETir4G & SERvicF 513 Gilmoure Drive Atomic Safety and LicensingR8bstd Silver Spring, MD 20901 U.S. Nuclear Regulatory Commission Wa:hington, DC 20555 Mr. Glenn 0. Bright Administrative Judge Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, DC 20555 In the Matter of CLEVELAND ELECTRIC ILLUMINATING COMPANY, ET AL.

(Perry Nuclear Power Plant, Units 1 and 2)

Docket Nos. 50-440 OL, 50-441 OL

Dear Administrative Judges:

As a supplement to Mr. Silberg's letter of June 19, I am enclosing copies of a recent letter from Cleveland Electric Illuminating Company to NRC indicating the anticipated fuel load readiness date for the Perry plant has been changed from June 1985 to September 1985.

Sincerely, Colleen P. Woodhead Counsel for NRC Staff

Enclosures:

As stated cc w/ encls.: Ms. Hiatt Mr. Lodge Mr. Silberg cc w/o encls.: Rest of service list B507010394 850621 PDR ADOCK 05000440 O PDR

P.o. Box 5000 - CLEVELAND. oHlo 44101 -

TELEPHONE (216) 622 9800 - lLLUMINATING BLOG. - $$ PUBLICSoVARE Serving The Best Location in the Nation MURRAY R. EDE. MAN VICE PnESIDENT NUCLE A R June 11, 1985 PY-CEl/NRR-0273 L Mr. B. J. Youngblood. Chief Licensing Branch No. 1 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 Unit 1 Progress Update

Dear Mr. Youngblood:

This letter is provided as an update of our progress on Unit 1 of the Perry Nuclear Power Plant. We are nearing completion of construction and testing and are preparing for fuel load. At this point we are 12 weeks negative with respect to the Project Master Plan fuel load date of June 14, 1985. Following is a summary of those activities which have occurred since our last update (December 20, 1984).

Construction An update of the various bulk construction quantities is provided in Attachment

1. The remaining bulk work is minimal and is not expected to impact our critical path. There are no hardware procurement problems which could prevent timely completion of construction.

Preoperational Testing All but nine (9) turnovers from Construction to Test have now been completed and preoperational testing is well underway. All diesel generator (Division 1, 2 and 3) related testing is complete with the exception of the Loss of Offsite Power Test. The Reactor Recirculation (533) integrated test is moving along rapidly now after a setback resulting from a reactor recirculation pump motor failure. Our preoperational test program is progressing as shown in Attach-ment 2.

Licensing -

FSAR verification is nearing completion. The FSAR has been updated through Amendment 19 to include most of the revisions associated with this FSAR verification effort. The remaining revisions will be incorporated into the FSAR in the near future.

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B. J. Youngblood June 11, 1985

PY-CEI/NRR-0273 L Technical Specifications are in the final Proof and Review stage. Resolution I s

of all NRR, Region III and CEI comments is scheduled to be completed by July 5, l

1985. Final draf t issuance is scheduled for July 15, 1985.  ;

SER Issue Resolution is nearing completion with only five (5) vutstanding j

j Issues and eleven (11) Confirmatory Issues remaining to be resolved. Our '

potential License Condition status and schedule for closeout has been discussed with your staff and we anticipate including this summary as Appendix 1B to the FSAR.

i The TDI diesel engine reliability program is essentially complete. The Phase I and II (DR/QR) efforts are complete with the exception of the 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> run and

, follow-up inspection. Preoperational testing is also complete with the exception of the Loss of Offsite Power Test. Torsiograph testing is complete and the results satisfactory. These results are being transmitted to NRC for review.

The PNPP Mechanical Equipment Qualification (EQ) files were submitted to NRC on April 3, 1985 and updated on May 22, 1985. We anticipate closure of NRC's EQ concerns with these submittals.

Revision 4 to the Emergency Plan was submitted on February 20, 1985. Safety 4

Evaluation Report Supplement 6 issued in April, 1985, responded to this revision by closing all NRR open items with the exception of the FEMA findings and testing of the prompt alerting and notification (PAN) system. The PAN system test is scheduled for June 12, 1985. All FEMA findings but one (1) have now been satisfactorily resolved. The state and county agencies are working with FEMA to resolve this remaining open item. The FEMA findings will be

, documented in a future supplement to the SER.

NRC conducted an Emergency Preparedness Appraisal February 25 to March 7, 1985.

The appraisal report issued May 1,1985, identified several open items to which

, we responded on May 30, 1985. We anticipate that all these items will be closed.

An Appendix R to 10CFR50 fire protection audit was held on-site March 10-22, 1985. The staff concluded that we are making satisfactory progress in the implementation of the fire protection requirements, and identified areas yet to be completed. Revision 4 to the Fire Protection Evaluation Report was submitted on May 23, 1985 and response letters to all the trip report items have been sent. We are in the process of resolving the Region III open items resulting from this audit and intend to have them resolved by fuel load with full implementation prior to exceeding 5% power. ,

The Instrument Control Systems Branch (ICSB) Audit was held April 23-25, 1985.

During this audit, we demonstrated completion of tasks required to resolve several confirmatory issues.

4

. B. J. Youngblood June 11, 1985 PY-CEI/NRR-0273 L The Detailed Control Room Design Review (DCRDR) Pre-Implementation Audit was conducted April 9-12, 1985. The audit revealed that our Control Room Design Review methodology was acceptable. The majority of the Human Engineering Deficiencies (HED's) will be resolved by fuel load, with any remaining HED's being resolved by the first refueling outage.

Revision 5 to the PNPP Security Plan was submitted to NRC on May 15, 1985.

This revision satisfies NRC's concerns expressed in Safety Evaluation Report Supplement 5. The Primary Access Control Point has been turned over to the Perry Plant Operations Department and will be placed in service in July 1985.

The PNPP Special Nuclear Naterials License was issued onMarch7, 1985.

The remaining licensing activities required for fuel load have been discussed with our NRC Project Manager, John Stefano, and we are working toward a mutually satisfactory schedule for closure. The commitment tracking system (LAPP) is being utilized to track these licensing commitments.

We intend to issue a Progress Update monthly f rom now to fuel load. If you have any comments or questions on the above information please inform us as soon as possible. We will also be prepared to discuss the above items in the future with you.

Very truly yours, Murray R. Edelman b

Vice President Nuclear Group HRE:njc Attachments cc: Jay Silberg, Esq.

John Stefano (2)

J. Grobe

ATTACHMENT I NRC STATUS TRACKING

- % COMPLETE -

THROUGH MAY 1985 PROGRAM PERRY *1 PERRY + 2 SITE PREPARATION 100.0 100.o CONTAINMENT-CONCRETE 100.0 94.8 CONTAINMENT-PRE-STRESS N/A N/A CONTAINMENT-STEEL 99.7 95.8 STRUCTURES 99.o 88.8 REACTOR PIPING 100.0 14.2 OTHER PIPING 99.9 19.4 REACTOR PRESSURE VESSEL 100.0 98.8 COMPONENTS 98.8 35.2 ISI/ PSI PIPING EXAMINATIONS 100.0 15.o PIPE SUPPORTS 99,8 (1) 15.8 FUEL RACKS too.o o.o ELECTRICAL-COMPONENTS & SYSTEMS 98.8 (2) 27.4 ELECTRICAL-CABLE & TERMINATIONS 99.6 0.0 l

INSTRUMENTS-COMPONENTS & SYSTEMS 97.7 2.8 INSTRUMENTS-CABLE & TERMINATIONS 99.8 (3) 11 6 (1) INCLUDES SNUBBER AND SPRING CAN INSTALLATI'ON. -

(2) DECREASE FROM LAST PERIOD IS DUE TO ADDITIONAL SCOPE 1 AND MINOR MODIFICATIONS TO BALANCE-OF-PLANT CONDUIT.

(3) CABLE ONLY. REMAINING TERMINATION COUNT UNDER ENGINEERING REVIEW DUE TO l RECENT SCOPE ADDITIONS (e.g., computer and security circuits).

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