ML20197E917
| ML20197E917 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 12/18/1997 |
| From: | Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Pearce L COMMONWEALTH EDISON CO. |
| References | |
| 50-254-97-18, 50-265-97-18, NUDOCS 9712300104 | |
| Download: ML20197E917 (2) | |
See also: IR 05000254/1997018
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Doomier 18, 1997
Mr. L W. Pearce
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Site Vice President
Quad Cities Station
Commonwealth Edison Company
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22710 206th Avenue North
Cordova,IL 61242
SUBJECT:
NOTICE OF VIOLATION (NRC INSPECTION REPORTS 50 254/97018(DRS);
50-265/97018(DRS))
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Dear Mr. Pearce:
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This will acknowledge receipt of your letter dated December 10,1997, in response to
our letter dated November 10,1997, transmitting a Notice of Violation associated with the
above mentioned inspection report at the Quad Cities Nuclear Power Station. We have
reviewed your corrective actions and have no further questions at this time. These corrective -
sctions will be examined during futurs inspections.
Sincerely,
/s/ J. Jacobson
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John A. Grobe, Director
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Division of Reactor Safety
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Docket Nos. 50 254; 50-265
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Enclosure:
Lir did 12/10/97 L. W. Pearce
Quad Cities to USNRC
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December 18, 1997,
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President & Chief Nuclear Officer
M. Wallace, Senior Vice President,
Corporate Services
E. Kraft, Vice President, BWR Operations
D. A. Sager, Vice President,
. Generation Support
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D. Farrar, Nuclear Regulatory -
Services Manager
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- 1. Johnson, Licensing Operations Manager
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Document Control Desk Licensing
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Quad Cities Station Manager
C. C. Peterson, Regulatory Affairs Manager
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Richard Hubbard
Nathan Schloss, Economist,
Office of the Attorney General
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State Liaison Officer
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Chairman, Illinola Commerce Commicolon
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W. D. Leech, Manager of Nuclear,
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MidAmerican Energy Company
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Distributior)
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Docket File w/ encl
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Rlli Enf. Coordinator w/enci
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PUBLIC IE 01 wlenci
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LPM, NRR w/ encl _
J. L. Caldwell, Rlil w/ encl
R. A. Capra, NRR w/enci
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SVP 97 280
December 10,1997
United States Nuclear Regulatory Commission
Washington, D. C. 20555
Attention:
Document Control Desk
Subject:
Quad Cities Nuclear Power Station Units 1 and 2
NRC Inspection Report Numbers 50 254/97018 and 50-265/97018
NRC Dockel No. 50 254 and 50 265
Reference:
(a) J. A. Grobe (USNRC) letter to L. W. Pearce (Comed),
NRC Inspection Report 50 254/97018(DRS); 50-265/97018(DRS)
and Notice of Wlation, Dated November 10,1997
(b) R. M. Pulsifer (USNRC) letter to D. L. Farrar (Comed), SER for Flaw
Evaluation of Recirculatl .a Piping Welds Quad Cities Nuclear Power
Station Unit 1, Dated May 10,1996 (TAC NO. M95127)
(c) L. W. Pearce (Comed) letter to USNRC, Response to NRC SER
(TAC No. M95127), Dated November 20,1997
Enclosed is Commonwealth Edison's (Comed's) response to the Notice of Violation
(NOV) and Comed's plans to address the concern regardiah the fatigue usage factor for
the reactor vessel head studs as requested in Reference (a).
The report cited one Severity LevelIV $lolation. The ,iolation citee that the licensee
had failed to implement prompt corrective actions for the ineffective induction heat stress
improvement (IHSI) process utilized on Unit I recirculation pipe welds." This was of
concem since the associated welds were not ieclassified to be inspected in accordance
with Generic letter (GL) S8 01 Category D schedule. Please refer to Attachment A for
Comed's response to the NOV.
Ples'e refer to Attachment B for Comed's plan to address URI 50-254(265)/97018-04
regarding the fatigue usage factor for the reactor vessel head studs.
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SVP.97 280
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December 10,1997
This letter contains the following commitment with regard to the NOV:
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laservice laspection administrative procedure QCTP 0410-01 will be revised to
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include a requirement to reclassify welds based on results of examinations within 90
days of startup following the refuel outage when examinations were performed (e.g. to
coincluie wiih issuance of the 90 Day Summary Report). Thl will ensure management
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expectations of prompt corrective actions is reinforced. This action will be tracked
under NTS# 2541009701804.01 and completed by March 15,1998.
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This letter contains the following commitments with regard to the reactor vessel head
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studs:
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Finalise the preliminary engineering evaluation and submit a summary of the results to
the NRC. This action will be tracked under NTS# 2541009701804.02 and completed
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by December 31,1997.
- Based on the abnve tesulis, prepare and submit a revision to the UFSAR to securately
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resect the actics Comed is tsking to assure the continued integrity of the RPV
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closure studs. A revision to de UFSAR will be performed in accordance with Quad's
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current program. In co$anction, submit a plan detailing the necessary long term
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actions to the NRC for review. These actions wil! be tracked under
NTS# 2541009701804.03 and completed by January 30,1998
Ifyou have any questions concerning this letter, please contact Mr. Charles Peterson,
Regulatory Affairs Manager, at (309) 634 2241, extension 3609.
_ /Gir/
L. W. Pearce
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Site Vice President
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, Quad Cities Station
Attachment (A), " Response to Notice of Violation"
Attachment (B), " Plan to Address Reactor Vessel liead Stud Fatigue Usage Factor
Concern"
cc:
A. B. Beach, Regional Administrator, Regicn III
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R. M. Pulsifer, Project Manager, NRR
C. G. Miller, Senior Resident Inspector, Quad Cities
W. D. Leech, MidAmerican Energy Company
D. C. Tubbs, MidAmerican Energy Company
- F. A. Spangenberg, Regalatory Affairs Manager, Dresden
INPO Records Center
OtSce ofNuc; ear FacWty Safety,IDNS
DCD License (both electronic and hard copies)
~ M. E. Wagner, Licensing, Comed
SVP Letter File
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ATTACIIMENT A
RESPONSE TO NOTICE OF VIOLATION
SVP-97 280
(Page1of!)
NOTICE OF VIOLATION (50-254(265)/97018-03)
10 CFR 50, Appendix D Criterion XVI requires in part that measures shall be established
to assure that conditions adverse to quality, such as failures, deficiencies, and
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nonconformances are promptly identified and corrected.
Contrary to the above, on September 25,1907, the inspector identified that the licensee
had failed to implement prompt correctivri actions for the ineffective induction heat stress
improvement process utilized on the Unit I recirculation pipe welds.
This is a Severity Level IV Violation (Supplement I). (50-254(265)/97018-03).
REASON FOR TIIE VIOLATION:
Quad Cities Station concurs with the violation.
The cause of this violation was fanjure to take prompt corrective actions to reclassify the
, associated welds to implement the Category D inspection schedule for future GL 88-01
examinations for Unit 1 Category C welds which were stress improved with the IHSI
process.
LORRECTIVE STEPS TAKEN AND RESULTS ACIIIEVED
To correct the violation, Reference (c) was submitted formally docketing Comed's plan to
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implen.ent the Category D inspection schedule for Unit 1 GL 88-01 Category C welds
which were stress improved with the IllSI process as discussed in Reference (b).
CORRECTIVE STEPS TAKEN TO AVOID FURTIIER VIOLATIONS
Inservice Inspection administrative procedure QCTP 0410-01 will be resised to include a
requirement to reclassify welds based on results of examinations within 90 days of startup
following the refuel outage when examinations were performed (e.g. to coincide with
issuance of the 90 Day Summary Repon). This will ensure management expectations of
prompt corrective actions is reinforced. This action will be tracked under
NTS# 2541009701804.01 and completed by March 15,1998.
DATE WilEN FULL COMPLIANCE WAS ACHIEVED
Full compliance was achieved on November 20,1997 when Reference (c) was docketed.
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ATTACHMENT B
PLAN TO ADDRESS RPV STUD FATIGUE
USAGE FACTOR CONCERN
SVP-97-180
(Page1of1)
The MRC identified a concern (URI 50-254(265)/97018-04) regarding the fatigue usage
factor for the reactor vessel (RPV) head studs. As stated in UFSAR Section 3.9.1.1.1,
based upon GE Report SASR 89-02 " Vessel Fatigue Evaluation Considering Revised
Thermal Cycles for Quad Cities Station Units 1 and 2," submitted to NRC October 2,
1990, the RPV closure studs are predicted to reach a fatigue cumulative usage factor
(CUF) of 1.0 in 1998. The UFSAR states,"which will then require a more rigorous visual
examination or replacement". Since Unit I and 2 are scheduled to continue operation into
1998, and these evaluation actions have not been completed, the NRC requests that
Comed submit the planned corrective actions and schedule to resolve this issue.
To address the issue, a preliminary evaluation was performed, using methodology applied
in the 1990 evaluation, to determine the accuracy of the 1990 prediction of the studs
reaching a CUF of 1.0 in 1998. The original evaluation was based on predicted cycles,
nis preliminary valuation is based on the actual cycles experienced as of
October 23,1997. Then, using actual cycles, averaged over the last five years, predict
when a CUF of1.0 will be attained.
The results of the preliminary evaluation conservatively determined that the studs will not
exceed a CUF of 1.0 during the next two (2) years for both Quad Cities Unit 1 and 2.
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Therefore, the RPV studs are predicted to reach a CUF of 1.0 no earlier than the year
2000.
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The following actions are required to resolve this issue:
Finalize the preliminary engineering evaluation and submit a summary of the results to
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the NRC. This action will be tracked under NTS# 2541009701804.02 and completed
by December 31,1997.
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Based on the above results, prepare and submit a revision to the UFSAR to accurately
e
reflect the actions Comed is taking to assure the continued integrity of the RPV
closure stude. A revision to the UFSAR will be performed in accordance with Quad's
current program. In corjunction, submit a plan detailles the necessary long term
actions to the NRC for review. These actions will be tracked under
NTS# 2541009701804.03 and completed by January 30,1998
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