ML17347A512
| ML17347A512 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 05/21/1987 |
| From: | Reyes L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Woody C FLORIDA POWER & LIGHT CO. |
| References | |
| NUDOCS 8706030496 | |
| Download: ML17347A512 (8) | |
Text
"ACCESSION NBR FAC IL:50-250 251 AUTH. NANE REYESe L. A.
REC IP. NANE MOODY'.
0'EGULATORY I
RNATION DISTRIBUTION SYST (R IDS)
- 8706030496 DOC. DATE.: 87/05/21 NOTARIZED:
NO DOCKET Turkey Point Plant.
Unit 3i Florida Power and Light C
05000250 Turkey Point Plant>
Unit 4I Florida Pover and Light C
05000251 AUTHOR AFFILIATIGIN Region 2i Office of Director RECIPIENT AFFILIATION Florida Power 5 Light Co.
SUBJECT:
Summarizes 870505 meeting v/util at plant site re Augmented Insp Team findings h issues that may af feet plant. List of attendees encl.
DISTRIBUTION CODE:
IE4SD COPIES RFCEIVED: LTR / ENCL g SIZE:
TITLE: Summary of Significant Neeting with Licensee NOTES:
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RECIPIENT ID'ODE/MANE ac DONALD> D AEOD/DSP/TPAB NRR/DLPG/GAB N
S/ ILRB EG FILE 02 NRC PDR COPIES LTTR EN L 1
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LTTR 14 ENCL 13
MAY 211987 Docket Nos. 50-250, 50-251 License Nos.
DPR-31, DPR-41, orida Power and Light Company ATTN:
Mr. C. 0.
Woody Group Vice President Nuclear Energy Department P. 0.
Box 14000 Juno Beach, FL 33408
~ e.D Gentlemen:
SUBJECT:
MEETING SUMMARv - TURKEv POINT NUCLEAR PLANT - DOCKET NOS. 50-250 AND 50-251 This letter refers to the meeting conducted at your Turkey Point Nuclear Plant May 5, 1987.
The meeting involved a discussion on the Augmented Inspection Team (AIT) findings and other issues that.may affect restart of the units.
Enclosed is a summary of the meeting topics.
It is our opinion that this meeting w'as beneficial, and provided a better understanding of the restart issues and the status of 'your corrective actions.
In accordance with Section 2.790 of the NRC's Rules of Practice, "Part 2, Title 10, Code of Federal Regulations,"
a copy of this letter and the enclosures will be placed in the NRC's Public Document Room.
Should you have any questions concerning this matter, we will be pleased to discuss them.
Sincerely,
/ S Ae~~
I'.
Luis A.
Reyes=; Director Division of Reactor Projects 8706030096 870521 PDR ADOCK 05000250 8
PDR bcc w/encl:
g NRC Resident Inspector Document Control Desk State of Florida
Enclosures:
1.
Meeting Summary 2.
Attendance List c w/encls:
C M. Wethy, Vice President Turkey Point Nuclear Plant
. J. Baker, Plant Manager urkey Point Nuclear Plant
. Arias, Jr., Regulatory and Compliance Supervisor B 'lson:cdg o g /87 RII(
DMVerrelli 05/>/87 RII VBrownlee Osu /87
ENCLOSURE 1
MEETING SUMMARv At the conclusion of the Augmented Inspection Team (AIT) Exit briefing on May 5, 1987, representatives from Florida Power and Light Company (FPL) and the NRC met to discuss the various issues that could impact the restart of Turkey Point Units 3 and 4.
FPL's present schedule is for Unit 4 to restart on May 25 and Unit 3 to restart on June 15.
A list of attendees is contained in Enclosure 2.
The restart issues were divided into five areas:
- 1) follow-up on AIT findings (conoseal report);
- 2) diesel generator wiring errors;
- 3) proposed integrated sequencer tests; 4)
Raychem splices; and
- 5) effectiveness of engineering evaluations.
Much of the discussion concerning items 1) and
- 5) took place during the AIT Exit briefing.
Issue
- 1) AIT Findings Commitments were made by FPL to improve inspections, leak detection processes and engineering evaluations in order to prevent an incident such as this from re-occurring.
Many of these commitments are contained in FPL letter L-87-186, Report on Instrumentation Port Column Assembly Leakage.
The AIT Report, No. 50-251/87-16, will also summarize the team's findings and will concur in the restart of Unit 4 pending satisfactory completion of the applicable commitments, E
Issue
- 2) Diesel Generator Wiring Errors FPL recently identified wiring errors in the emergency diesel generator (EDG) protection circuitry and the 3B load sequencer.
Licensee repre-sentatives described their analysis of the cause of these errors and the proposed corrective actions.
These actions included functional tests of the "A"
EDG protective relaying, 100% inspection of the wiring in all four load sequencers, engineering analysis of sequencer circuitry for other "hidden" circuits and functional testing of these previously untested circuits.
The delayed start of the Containment Spray Pumps due to a small break Loss of Coolant Accident (LOCA) is an example of one of these untested circuits.
They have subsequently identified four other capabilities of the sequencer not previously tested (see Issue 3).
Additional information on this issue is contained in Inspection Report 50-250, 251/87-14.
Issue
- 3) Integrated Sequencer Test As a result of wiring errors discussed previously, FPL concluded that the "cross-talk" capability of the sequencers during a Loss of Offsite Power (LOOP) of,both units had never been adequately tested.
They committed to develop and perform such a test prior to restart of either unit.
A test of this type can only be properly performed with both units in cold shutdown.
The proposed test would be to interrupt offsite power to both
Enclosure 1
\\
units, allow the EDGs to energize the required shutdown
- loads, then to manually initiate a safety injection on one unit.
This test would then be repeated for the other unit.
NRC personnel cautioned that the test be carefully planned so as to not subject personnel and equipment to unnecessary hazards.
Also, that Regional personnel be kept aware of schedules, be provided test procedures and work closely with FPL personnel in order to monitor the test.
In subsequent telephone conversations on May 13,
- 1987, FPl committed to functionally test five circuits on each unit prior to restart of the applicable unit.
These tests will be monitored by NRC inspectors and documented in Inspection Report
- 250, 251/87-26.
Issue 4)
Raychem Splices FPL identified a large number of electrical cable splices with problems (installed incorrectly or lack of proper documentation).
The licensee has or will replace 1475 splices in Unit 3 containment and 879 splices in Unit 4.
The licensee plans to replace the remaining Unit 4 splices (in containment) during the next scheduled refueling outage.
They have developed a Safety Evaluation (SE) to iustify restart of Unit 4 prior to replacing all of the identified defective splices.
Their original schedule called for replacement of Unit 4 splices during the 1988 refueling outage;
- however, they decided to take advantage of the outage caused by the conoseal leakage and replace the more sensitive instrument splices.
The Safety Evaluation has been forwarded,to NRR for review.
Issue
- 5) Effectiveness of Engineering Evaluations FPL was asked to address this subject during the meeting due to NRC concerns in this area.
These concerns were raised due to perceived inadequacies as evidenced by the examples given in the SALP report (250, 251/86-27) and the Enforcement Action '86-20.
Nore recent issues include the conoseal leakage evaluation, seismic operability of EDG air receivers, and ICW check valve operability.
Licensee representatives discussed several areas of potential improvement including procedures, staffing and supervisory review of evaluations.
A gIP team has been formed to prepare an Engineering Guideline Document while instruction 01 3.2, Guidelines for the Preparation of Safety Evaluations, is being reviewed for adequacy.
FPL was informed during the meeting that an NRC
- inspection would be conducted to evaluate the licensee's performance in this area.
FPL felt confident about the results of this inspection since INPO has identified FPL's Standard Engineering Package as an Industry Good Practice.
~Summac Issue Subject Action Necessar for Restart AIT Findings NRC - Issue AIT Report FPL - Meet commitments in L-87-186
Enclosure I EDG Wiring Errors NRC - None FPL - Complete evaluation of wiring errors Sequencer Test NRC - Review Test Procedure, monitor test FPL - Complete functional testing of all identified circuits Raychem Splices NRC - Evaluate FPL SE concerning Raychem splices FPL - Complete splice repair work in I
Units 3 and 4 as presently scheduled Engineering Evaluations NRC - Conduct team inspection FPL - Initiate stated improvements in procedures, staffing and supervisory review
ENCLOSURE 2
LIST OF ATTENDEES NRC - FPL MEETING MAv 5 1987 Florida Power and Li ht Com an J.
F.
D.
C.
C.
J.
C.
R.
J.
D.
H.
E.
M.
F.
L.
W.
P.
P.
E.
J.
J.
H.
R.
M.
P.
J.
Arias, Jr.
Southworth Grandage Baker 0.
Woody W. Dickey M. Wethy J. Acosta K. Hays A. Chancy T. Young Preast J. Crisler G. Flugger F. Pabst J.
Pike L. Pace W. Hughes L. Anderson P. Mendieta W. Kappes E. Yaeger L. Wade J. Bowskill A. Roach L. Montgomery Regulation 8 Compliance Supervisor Maintenance Superintendent Operations Supernintendent Plant Manager Group Vice President Vice President Nuclear Operations Site Vice President Director, guality Assurance Director of Nuclear Licensing Plant Site Engineer Manager Project Site Manager APMG gC Supervisor Manager Technical Licensing Manager Mechnical Engineer Safety Engineer Group Licensing Supervisor HP Supervisor ISI Engineer Services Manager -
N PEP Manager Manager Nuclear Maintenance Site Engineering STA Lead Engineer STA Lead Elec./I&C Engr.
NRC J.
J.
G.
D.
D.
B.
A.
M.
J.
K.
R.
N.
H.
C.
G.
R.
A.
R.
L.
B.
W.
V.
Grace Sniezek Lainas McDonald Brewer Wilson Herdt Ernst MacDonald YanDyne Crlenjak Regional Administrator, RII Deputy Director, NRR Assitant Director, RII, NRR Project Manager, NRR Senior Resident Inspector, Turkey Point Section Chief, RII Branch Chief, DRS RII Deputy Regional Administrator, RII Resident Inspector, Turkey Point Resident Inspector, Turkey Point Senior Resident Inspector, St. Lucie
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