IR 05000333/1997011
| ML20216B418 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 03/04/1998 |
| From: | Wiggins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Michael Colomb POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| References | |
| 50-333-97-11, EA-98-001, EA-98-1, NUDOCS 9803130070 | |
| Download: ML20216B418 (35) | |
Text
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i March 4, 1998
!
EA 98-001 -
Mr. Michael J. Colomb Site Executive Officer New York Power Authority
!
James A.' FitzPatrick Nuclear Power Plant Post Office Box 41 Lycoming, NY 13093 SUBJECT: NRC SPECIAL INSPECTION REPORT NO. 50-333/97-11 Deor Mr. Colomb:
!
This refers to the specialinspection conducted between December 15,1997,and January 7,1998, et the FitzPatrick Nuclear Power Plant in Scriba, New York, the findings of which were discussed with members of your staff during an exit meeting on December 19,1997, and during a telephone exit meeting with Messrs. Zaremba and Abramsk on January 7,1998. During the inspection, apparent violations were identified involving an unreviewed ' afety question (USQ) in the modification of the control system s
for the Traversing incore Probe System (TIP) system and the inoperability of the TIP system primary containment isolation ball valves that resulted from this modification. The inspection report addressing these issues was previously forwsrded to you on -
.i January 28,1998. On February 19,1998, a predecisional enforcement conference
(conference) was conducted with you and members of your staff, to discuss the violations, their causes, and your corrective actions.
i During the conference, you provided your arguments that all nonsafety-related systems were assumed to fail (irrespective of failure mechanisms and the probability of failure)
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during a sostulated accident, therefore, you concluded that the original General Electric TIP system and the replacement Siemens system had the same failure mode. Consequently,
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you concluded that no unreviewed safety questions was introduced in your 1991 modification. We agree with you that no unreviewed safety questions was introduced in your 1991 modification for replacing the original General Electric TIP system with a Siemens system. Also, we found that you met your Technical Specifications requirements regarding the TIP system ball valves.
As a result of the inspection and the conference, we identified a concern associated with l
the process NYPA used to reevaluate the Siemens design for a USQ after the 1996 event.
It appears that NYPA concluded that no USQ existed based, in part, on a comparison of a failure modes and effects analysis developed by NYPA for the Siemens design to a similar analysis for a GE design documented in a GE Topical Report. However, upon questioning by the NRC, NYPA was unable to determine if NRC had accepted the GE Topical Report as the licensing basis for the FitzPatrick Tip control system. The more appropriate comparison would have been between the Siemens design and the FitzPatrick licensing basis contained in the Updated Final Safety Analysis Report.
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.9903130070 990304 TED PDR ADOCK 05000333
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Mr. Michael J. Cok>mb
'l No response to this letter is required. Your cooperation with us is appreciated.
Sincerely, ORIGINAL SIGNED EY:
James T. Wiggins, Director Division of Reactor Safety Docket No. 50-333 License No. DPR-59 Enclosures:
1. NRC Enforcement Conference Slides 2. NYPA Presentation Slides cc w/encis:
C. D. Rapr'eyea, Chairman and Chief Executive Officer E. Zeltmann, President and Chief Operating Officer R. Hiney, Executive Vice President for Project Operations J. Knubel, Chief Nuclear Officer and Senior Vice President H. P. Salmon, Jr., Vice President of Engineering W. Josiger, Vice President - Engineering and Project Management J. Kelly, Director - Regulatory Affairs and Special Projects T. Dougherty, Vice President - Nuclear Engineering R. Deasy, Vice President - Appraisal and Compliance Services R. Patch, Director - Quality Assurance G. C. Goldstein, Assistant General Counsel C. D. Faison, Director, Nuclear Licensing, NYPA K. Peters, Licensing Manager T. Morra, Executive Chair, Four County Nuclear Safety Committee Supervisor, Town of Scriba C. Donaldson, Esquire, Assistant Attorney General, New York Department of Law P. Eddy, Electric Division, Department of Public Service, State of New York G. T. Goering, Consultant, New York Power Authority J. E. Gagliardo, Consultant, New York Power Authority E. S. Beckjord, Consultant, New York Power Authority F. William Valentino, President, New York State Energy Research and Development Authority J. Spath, Program Director, New York State Energy Research and Development Authority
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Mr. Michael J. Colomb
Distribution w/ enc!s:
H. Miller, RA/W. Axelson, DRA Nuclear Safety Information Center (NSIC)
PUBLIC NRC Resident inspector Region 1 Docket Room (with concurrences)
J. Rogge, DRP R. Barkley, DRP R. Junod, DRP C. Hehl, DRP J. Lieberman, OE (2)
M. Satorius, OE D. Holody, ORA T. Walker, CRA L. Cheang, DRS W. Ruland, DRS J. Wiggina, DRS C. Miskey, DRS B. McCabe, RI EDO Coordinator S. Bajwa, NRR D.PNmsn,NRR D. Scranci, PAO M. Carnpion, Ri inspection PruEram Branch, NRR (IPAS)
R. Correia, NRR
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F. Talbot, NRR i
DOCDESK i
DOCUMENT NAME: A:\\FITZ9711.TIP T4 receive a copy of this document, indicate in the box:
"C" = Copy without attachment / enclosure
- E' = Copy with attachment / enclosure
- N"=
No copy OFFICE Rl/DRS Rl/DRS C-Rl/DRP l
Rl/DRS l
NAME LCheuig WRulandG)/JfL CHehl$gef JWiggins f DATE 03/02/98 03/t./.98 03/7 /98 03/.fi98 "
03/ /98 OFFICIAL RECORD COPY
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ENCLOSURE 1 Enforcement Conference A predecisional enforcement conference was held at NRC Region 1 office on February 19, 1998, to discuss the apparent violations in NRC inspection report 97-11 (EA No.98-001).
The presentation slides are attached.
Licensee Attendees:
M. Abramski, Senior Licensing Engineer W. Bennett, Senior Design Engineer
)
M. Colomb, Site Executive Officer, FitzPatrick
T. Daugherty, Director of Nuclear Engineering G. Goldstein, Attorney D. Ruddy, Director of Design Engineering A. Zaremba, Licensing Manager NRC Attendees:
i S. Bajwa, Project Director, NRR R. Barkley, Project Engineer, DRP, RI L. Cheung, Senior Reactor Engineer, DRS, Rl C. Hehl, Director, DRP, RI J. Rogge, Chief, Projects Branch 2A, RI W. Ruland, Chief, Electrical Engineering Branch, DRS, RI T. Walker, Senior Enforcement Specialist, ORA, RI J. Wiggins, Director, DRS, RI i
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FITZPATRICK TIP SYSTEM ENFORCEME:NT CO:NFERENCE
'
What happened:
+ In 1991, :NYPA replaced, under 50.59, the original GE Traversing In-core j
Probe (TIP) system with a Siemens Programmable Logic Controller based TIP system.
+ On September 16,1996,a technician shorted a relay with a screwdriver, causing a turbine and reactor trip. This also caused a block of the fast transfer to the reserve transformers, causing a loss of nonsaftey power, including power
'
to the TIP control system, and the activation of the containment isolation (CIS? signal.
Fim. con February 19,1998 J
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+ Upon power restoration, a failed power supply in the TIP system inserted an incorrect command to a TIP control unit, which caused all three primary containment isolation valves (CIVD to open in the presence of a valid containment isolation signal.
+ Part of the design basis for the three CIVs in the TIP system was specified in the FSAR section 7.5.9.2 (Revision 4, dated July 1993) which states that (for each TIP subsystem) a guide tube (primary containment isolation) ball valve opens only when the TIP is being inserted.
Fitz. con February 19,1998
.
.
- NRC Concerns
+ In 1991, NYPA failed to identify an Unreviewed Safety Question (USQ)
with the TIP modification.
l
+ The engineering review of the basis for
'
the TIP control system, a corrective action as stated in LER 96-10, April 1997, also failed to identify the USQ.
+ :NYPA replaced the nonsafety-related TIP power supply without understanding the installation instructions. Corrective actions for this problem were weak.
I Fitz. con February 19,1998
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