ML20136E377

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Forwards Matrix Containing Status of Significant Issues Identified from Recent Refueling Outage at Plant Unit 1
ML20136E377
Person / Time
Site: Saint Lucie 
Issue date: 07/19/1996
From: Landis K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Jerrica Johnson
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML17229A261 List: ... further results
References
FOIA-96-485 NUDOCS 9703130192
Download: ML20136E377 (3)


Text

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/ p neesk UNfTED STATES NUCLEAR REGULATORY COMMISSION 1

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101 MARIETTA STREET, N.W., Sufft 2500 0

ATLANTA, GEORGIA 3G3230100

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July 19, 1996 MEMORANDUM TO:

Jon R. Johnson, Acting Director Division of Reactor Projects FROM:

Kerry D. Landis, Chief g

Reactor Projects Branch 3 p

i Division of Reactor Projects i

SUBJECT:

READINESS TO RESTART FOLLOWING A R UELING OUTAGE -

ST. LUCIE UNIT 1 The enclosed matrix contains the status of significant issues identified from the recent refueling outage, considered necessary to be assessed and resolved prior to unit restart. The following documents were reviewed by the 1

identified responsible individuals to ascertain those items to' be included on the matrix.

REFERENCES RESPONSIBILITY IFS SRI /DRS LICENSEE RESPONSES SRI /DRS I

.' CAL /0RDER SRI /PM i

LICENSE AMENDMENTS PM i

BULLETINS (BUL)

PM l

GENERIC LETTERS (GL)

PM-MAJOR MODIFICATIONS SRI EMERGENT ISSUES SRI /PM Each item listed in the enclosure has been assessed and either closed based upon satisfactory completion or. remains open pending resolution as indicated.

Pending satisfactory closure of the indicated open items, we have no concerns 1

which would preclude the restart of the unit.

The planned date of entering i

Mode 2 (startup) is July 22, 1996.

i Please contact me with'any questions concerning the restart.

Docket No. 50-335 License No. DPR-67 n

Attachment:

St. Lucie Unit 1 1996 Refueling Outage Items Status

Contact:

K. Landis, DRP 404/331-5509 j

9703130192 970306 1

PDR FOIA L,

8INDER96-485 PDR a

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St. Lucie Unit 1 1996 Refueling Outage items Status 1

ACTIVITY / ISSUE NRC LEAD REF. NO.

COMENTS STATUS

]

Verify Unit 1 SRI IR 96-06 PM SFP CLB review Closed

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procedure for maintaining SFP temp

< 150 F Verify SFP heat load SRI IR 96-06 PM SFP CLB review Closed calc performed Verify procedure to SRI IR 96-06 PM SFP CLB review Closed ensure boron concentration >1720 DDa Unit Shutdown SRI IR 96-06 Closed RCS' nozzle SRI Work complete.

Open 1

Licensee reports inspections SAT. SRI to review data.

SRI IR 96-06 Closed Integrated Safeguards Testing Pzr code safety SRI IR 96-06 Closed valve replacement / flange

)

mods Visual examination SRI IR 96-08 Closed of bottom of RWT EDG Radiator SRI IR 96-08 Closed Replacement S/G tube inspection RI GL 95-03 100% bobbin 100% HL Closed Bul 89-01 MRPC 3% CL MRPC 100% Westinghouse plug SG Tube Plugging-Wiens/NRR License Not re' quired based Closed Related TS Amendment Amendment on level of tube No. 145 plugging (<25%),

but requested and issued on 7/9/96.

P ATTACINENT i

A.

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1 i'

ACTIVITY / ISSUE NRC LEAD REF. NO.

COMMENTS STATUS Adequacy of SG Tube SRI IR 96-11 Verify adequacy of Open Plug Installation licensee review for l

plug installation records.

]

Rx Disassembly SRI IR 96-06 Closed Modify relief valve RI LER 95-06 SDC valves V3468 Open l

i setpoints and and V3483. This blowdown values item is to satisfy a commitment made in the LER.

1 l

RV Core Barrel RI IR 96-06 Closed j

inspection 10 yr ISI IR 96-08 Wide Range Nuclear SRI IR.96-11 Verify an. adequate Open Instrument basis.for i

Operability concluding that j

noise problems have been adequately j

addressed.

Unit Startup/

RI Plant Resident-coverage Open Physics Testing Procedures Instrument sensing RI LER 95-01 This item included Open i

line blowdowns to satisfy LER commitment.

Work complete paperwork l

needs reviewed.

i EDG Relay socket RI LER 95-07 This item included Open replacements IR 96-06 to satisfy LER commitment.

Work i

complete paperwork i

needs reviewed.

3 4

Evaluation of SRI N/A Per NRR, evaluation Closed whether Unit was must be completed outside design basis prior to startup.

1 based upon results Licensee will of in-situ pressure inform NRC if they i

tests.

were outside design i

basis via normal channels.

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