ML17301A042

Advises That License Conditions for 5% Power Completed. Power Ascension Will Be Commenced Upon Completion of Low Power Physics Testing

ML17301A042
Person / Time
Site:	Saint Lucie
Issue date:	06/06/1983
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
REF-SSINS-6820 IEB-77-05, IEB-77-05A, IEB-77-5, IEB-77-5A, IEB-79-02, IEB-79-14, IEB-79-2, IEB-80-06, IEB-80-11, IEB-80-12, IEB-80-15, IEB-80-6, L-83-348, NUDOCS 8306130268
Download: ML17301A042 (10)

Text

Za- P. X 14000, JUNO BEACH, FL 33408 p

FLORIDA POWER & LIGHT COMPANY June 6, 1983 L-83-348 Office of Nuclear Reactor Regulations Attention: Mr. Darrell G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Eisenhut:

Re: ST. LUCIE UNIT NO. 2 DOCKET NO. 50"389 COMPLETION OF LICENSE CONDITIONS FOR 5% POWER The purpose of this letter is to inform you that Florida Power & Light Company (FPL) has satisfied the 5% power license conditions, which are described in Section 2 and Attachment l of the St. Lucie Unit No. 2 Operating License. Upon completion of Low Power Physics Testing, FPL will be ready to commence Power Ascension.

Please find attached a description of e'ach license condition and how FPL has satisfied the license condition.

Very t ly yours,

'obert E. Uhrig Vice President Advanced Systems and Technology REU/RJS/JES/rms Attachment cc: J.P. O'Reilly, Region II Harold F. Reis, Esquire

---

eko60~

830b13026 8 050003EH

.

t

'POR lr goOCK i

pDR LI PEOPLE... SERVING PEOPLE

l

~ I

LICENSE CONDITION FOR 5% POWER

ITEMS I ECTION 2 OF ST. LUCIE UNIT NO. LICENSE 2.C.4. Environmental uglification of Mechanical and Electrical E ui ment (Section 3.11.5 SSER 3)*

Prior to exceeding 5% of rated thermal power, the licensees shall complete and submit for NRC staff review and approval the analysis requited by 10 CFR 50.49(i).

Status: FPL via letter L-83-329, dated May 26, 1983, provided the information required by 10 CFR 50.49(i). The letter completes all requirements for this license condition.

2.C.8. Continuous Containment Pur e S stem (Section 6.2.4 SSER 3)

Prior to exceeding 5% of rated thermal power, the licensees will make the necessary modifications to assure the operability of the Continuous Purge System in the event of a loss of coolant accident.

Status: 1. FPL via letter L-83-286, dated May 10, 1983,,

provided the results of a modified calculation which showed that the maximum flood level would not submerge the supply line discharge entering containment. Following review of this letter by the NRC staff some additional 'nformation was requested. This additional information was submitted via FPL letter L-83-328, dated May 25, 1983. This completes all action by FPL for this portion of the license condition.

2. The damper between the debris screen and the .inboard containment isolation valve has been removed and this was verified by a Region'I inspector. This completes all 'actions by FPL on this portion of the license condition.

2.C.13. Fire Protection (Section 9.5.1.11(a) and ~ (b) SSER 3)

The licensees shall implement the fire protection program on a schedule specified in Section 9.5.1.11(a) and (b) of Supplement No. 3 to the Safety Evaluation Report.

Status: During meetings on June 2, 1983, with the Regional Office and your staff, the implementation of the Fire Protection System was discussed. It was understood that the present design and construction status satisfies this license condition, and that the final close out of the Fire Protection System'ask will be performed by the Regional Office.

2.C.17(b) Control Room Desi n Review (I.D.l A endix E Also Part of A endix C SSER 1 SSER 3)

Prior to exceeding five (5) percent of rated thermal power, the licensees shall complete correction of the human engineering discrepancies as noted in Appendix E of this license.

Status: During meetings on June 2, 1983, with the Regional Office and your staff, the correction of the human factors engineering discrepancies was discussed. It was understood that the present design and construction status satisfies this license condition and that the final close out of the discrepancies will be performed by the Regional Office.

2.C.17(c) Reactor Coolant S stem Vents (II.B.1 SSER 2)

Prior to exceeding five (5) percent of thermal power, FPL shall have the reactor coolant system vents installed and operational.

Status: The Reactor Coolant System Vents have been installed and are fully operational. This completes all action by FPL on this license condition.

2.C.17(e) In-Containment Hi h Ran e Radiation Monitors (II.F.l(2c) SSER 3)

Prior to exceeding five (5) percent of rated thermal power, FPL shall have the in-containment high range radiation monitors installed and operational.

I Status: The In-Containment High Range Radiation Monitors are installed and fully operational. This complet'es all FPL action on this license condition.

ITEMS ON PAGE 2 OF ATTACHMENT 1 OF ST. LUCIE UNIT NO. 2 LICENSE I. The licensee will complete, to the satisfaction of NRC Region II, the requirements of the following bulletins:

A. Pipe support base plate designs using concrete expansion anchor bolts (79-BU"02).

B. Seismic analysis for as-built safety-related piping systems (79-BU-14).

C. Engineered Safety Feature (ESF) reset controls (80-BU-06).

D. Decay Heat Removal system operability (80-BU-12).

E. Electrical connector assemblies (77-BU-05)(77"BU-05A).

F. Masonry wall design (80-BU-ll)(CDR 82-.24).

G. Possible loss of emergency notification system (ENS) with loss of off"site power (80-BU-15).

Status:

A. A final report was submitted to the NRC via FPL letter L-83-339, dated June 1, 1983. This completes all FPL action on this license condition.

B. A final report was submitted to the NRC via FPL letter L-83-340, dated June 1, 1983. This completes all FPL action on this license condition. I C. This bulletin was closed out to the satisfaction of Region II.

D. This bulletin was closed out to the satisfaction of Region II.

E. This bulletin was closed out to the satisfaction of Region II.

F. A final report was submitted to the NRC via FPL letter L-83-319, dated May 24, 1983. This completes all FPL action on this license condition.

G. This bulletin was closed out to the satisfaction of Region II.

II. The licensee will resolve, to the satisfaction of NRC Region II, the following IE Notices:

A. Design misapplication of Bergen-Paterson standard strut restraint clamp (IEN 83-13).

B. Failure of General Electric type HFA relays (IEN"82"13).

Status:

A. All information was provided to the Region II inspectors.

This completes all FPL action on this license condition.

B. This notice was closed out to the satisfaction of Region II.

0 a a + ~-

'

1 I ~

III. The licensee will resolve to the satisfaction of NRC Region II the following open items:

A. Review shielding adequacy of CVCS letdown monitor sample lines (82"70"02).

B. Conduct an accountability drill for both Units 1 and 2 following implementation of the Unit 2 Security Plan (82-05-10).

C. Program to review and document 10 CFR 50;59 evaluations for unreviewed safety questions for tests and experiments (82-64-01).

D. Evaluate need for shielding of penetrations in ion exchange cubicle and spent resin tank valve gallery (82"70-05).

Status:

A. This inspector item was closed out to the satisfaction of Region II.

B.'his inspector item was closed out to the satisfaction of Region II.

C. This inspector item was closed out to the satisfaction of Region II.

D. This inspector item was closed out to the satisfaction of Region II.

~

e'4 I s

~

~1 IV. The licensee will resolve to the satisfaction of NRC Region Ii, the issue of proper labeling and accessibility control of motor operated valve thermal overload protection bypass switches and control room(remote shutdown panel control diversion switches.

Status: This item was closed out to the satisfaction of Region II.