ML17213A545

Discusses NRC Understanding of Core Load Schedule.List of Licensing Actions Not Yet Resolved to NRC Satisfaction Encl

ML17213A545
Person / Time
Site:	Saint Lucie
Issue date:	09/10/1982
From:	Novak T Office of Nuclear Reactor Regulation
To:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
References
NUDOCS 8210080340
Download: ML17213A545 (8)

Text

September.

10, 1982 Docket No.

50-389 Dr. Robert E. Uhrig Vice President Florida Power 8 Light Company Post Office Box 529100 Miami, Florida 33152

Subject:

St. Lucie Plant, Unit No. 2, Construction Completion Date On August 12, 1982, the NRC Division of Licensing (Hr. Frank J. Hiraglia and Hr. Victor Herses),

discussed with your representatives (Mr. Dotson, tlr. Boissy and Hr. Sheetz) schedular requirements of remaining licensing actions to support your October 28, 1982 core load date.

Your representatives noted to the staff that the core load schedule still shows a twelve week slippage but intensive efforts were being made to identify improvements to reduce this figure.

Presently, the staff's understanding of the situation is as follows:

1.

The critical path variance for completion of Unit 2 is approximately 14 weeks behind schedule as reported in your "St. Lucie Unit 2 Construction/Startup Monthly Startup Report", which was submitted by your letter L-82-356 dated August 16, 1982.

2.

The NRC Caseload Forecast Panel visit to St. Lucie 2 on June 8-10,

1982, and review of subsequent information you provided us, leads us to estimate a date beyond your October 28, 1982 core load date.

3.

A number of FPSL licensing actions, as indicated in Enclosure,l have yet to be resolved to the staff's satisfaction.

4.

FPBL identified in their May 4, 1982 letter, several engineering and construction work items that were not expected to be completed by core load.

In our letter response of July 26, 1982, we stated that the justification for six of these items are unacceptable; therefore, FPBL is expected to complete these items before core load unless a

satisfactory justification is provided.

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c' Dr. Robert E. Uhrig September 10, 1982 5.

FP&L has scheduled (by telecon between Hr. Fincher, St. Lucie plant Training Supervisor and Hr. Boger, NRC, Section Leader) with the NRC Operator Licensing Branch to administer the initial operator licensing exams to prospective St. Lucie 2 operators in December 1982.

As discussed in a conference call with llr. Delpastry, tlr. Kaminsky and you on September 8 and 9, 1982, we agreed to meet later this month to discuss the schedule for plant completion and issues which must be resolved prior to issuance of the operating license.

This meeting will permit us to determine what resources and priorities will be needed to assure that the licensing process will not unnecessarily be a critical path item which would delay reactor startup of St. Lucie Plant, Unit 2.

Sincerely, OrijjTna1 signed by:

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

Enclosure:

As Stated cc w/enclosure:

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LUC IE Dr. Robert E. Uhrig, Vice President Advanced Systems and Technology Florida Power 5 Light Company P. 0.

Box 529100 Miami, Florida 33152 Harold F. Reis, fsq.

Lowenstein, Newman, Reis, Axelrad 5 Toll 1025 Connecticut

Avenue, N.M.

washington, O.C.

20036 Norman A. Coll, Esq.

Steel 'Hector 8 Davis 1400 Southeast First National Bank Building Miami, Fl ori da 33131 Mr. Martin H. Hodder 1131 N.

E. 86th Street Miami, Florida 33138 Resident Inspector St. Lucie Nuclear Power Station c/o U. S. Nuclear Regulatory Comnission 7900 South AlA Jensen Beach, Florida 33457 U. S. Nuclear Regulatory Commission 101 Marietta Street Suite 3100

Atlanta, Georgia 30303

ENCLOSURE I FLORIDA POWER 8 LIGHT COliPANY LICENSING ACTION ITEMS FOR ST.

LUCIE AS OF SEPTEMBER 9 1982 SER Section 3.8.4 3.9.2.3 3.9.3.2 3.9.6 3.10 3.11 4.2.3.1(a) 4.2.3.1(b) 4.2.3.1(c) 4.2.3.1(d) 4.2.3.1(g) 4.2.3.1(h) 4.2.3.2(g) 4.2.3.3(d) 5.2.4 5.2.4 5.4.3 5.4.3 6.3.2 6.6 Description of Item Evaluation results using NRC criteria of masonary walls Correlation of the St. Lucie 2 observed vibrational characteristics with the results from the prototype reactors Operability gualification of Pumps and Valves Leak tight integrity of pressure isolation valves procedure for Unit 2:

Seismic and Dynamic gualification of Seismic Category I Mechanical and Electrical Equipment Environmental guali fication of Saftey-Related Electrical Equi pment Design stress and strain analysis for the fuel assembly fuel rod BPR and CEA Stain fatigue analysis Provide results of CEA fretting analysis Results of the CEA axial growth documented in FSAR Complete analysis for burnable poison rod Fuel rod mechanical fracture by an externally applied force

( related to 4.2.3.3(d))

Structural damage from external forces Pre-Service inspection data of 'reactor vessel Relief request from the ASNE pre-service inspection of Class 1

Natural circulation and boron mixing test report Upper head voiding a) modify EOP to prevent voiding b) demonstrate sufficient emergency feedwater available Results of.sump vortex test Relief request from the ASNE pre-service inspection of Class 2

8 3

SER Section Descri tion of Item 7.2. 5 Provide summary of types of tests and acceptance criteria for surge 5 fault testing.

9.5.1 Fire Protection Items:

a) 9.'5.1.1.8 b) 9.5.1.2.D Standpipe Hose Stations (Fuel Handling Building)

Fire detection Systems used to actuate fire suppression systems c) 9.5.1.5.a Fire detection coverage zn control room d) 9.5.1.5.d Day tank curbing in diesel generator room e) 9.5.1.5.e f) 9.5.1.3.a Fire detection in battery room Fire barrier penetration seals g) 9.5. 1.6 Safe shutdown capability 15.6.3 15.10.2 15.10. 2 Provide confirmation that as a result of boron TS set points the analysis demonstrated sufficient operator time Provide confirmation analysis demonstrating a small feed-water line break will not result in exceeding 1105 of design pressure as noted in SRP 15.2.8 Submit justification regarding consideration of single failure and time of MSIS actuation 15.10.4 15.10.5 The analysis of Steam Generator tube rupture events usin CESEC III computer program ure even s using CESEC analysis for inadverdent opening of pressurizer relief valve Resolve control room design review audit items

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