ML20203D026
| ML20203D026 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 12/10/1997 |
| From: | Pearce L COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 50-254-97-18, 50-265-97-18, GL-88-01, GL-88-1, NUDOCS 9712160086 | |
| Download: ML20203D026 (4) | |
Text
_
o,ninn,n a ca w,, o.,,ip.un qu a oncu.m..
s.iao.,
l 2[lO 2tKdll A%- y 4 d6 6f1ll Cor dm. II. bil,'t
- 10 l'el.M r) M 4 JJ il 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 Docket 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 Violation, Dated November 10,1997 (b) R. M. Pulsifer (USNRC) letter to D. L. Farrar (Comed), SER for Flaw Evaluation of Recirculation 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 Commanwealth Edison's (Comed's) response to the Notice of Violation (NOV) and Comed's plans to address the concern regarding the fatigue usage factor for the reactor vessel head studs as requested in Reference (a).
Tha report cited one Severity Level IV violation. The violation cited "that the licensee had failed to implement prompt corrective actions for the ineffective induction heat stress improvement (IIISI) process utilized on Unit I recirculation pipe welds." This was of concern since the associated welds were not reclassified to be inspec'-d in accordance with Generic letter (GL) 88-01 Category D schedule. Please refer to Attachment A for Cc,mEd's response to the NOV.
Please 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.
g 9712160006 971210 PDR ADOCK 05000254 j
G PDR
- - ~.. -. -.-.- - - -
USNRC SVP-97-280 2
December 10,1997 This letter contains the following commit:nent with regard to the NOV.
Inservice Inspection administrative procedure QCTP 0410-01 will be revised to e
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. te J
coincide with issuance of the 90 Day Summary Report). This vill ensure management 4
expectations of prompt corrective actions is reinforced. This action will be tracked under NTS# 2541009701804.01 and completed by March 15,1998.
4 This letter contains the following commitments with regard to the reactor vessel head studs; i
Finalize the preliminary engineering evaluation and submit a summary of the results to e
the NRC. This action Wil be tracked under NTS# 2541009701804.02 and completed by December 31,1997.
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 studs. A revision to the UFSAR will be performed in accordance with Quad's current program. In conjunction, submit a plan detailing 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
- F If you have any questions concerning this letter, please contact Mr. Charles Peterson, Regulatory Affairs Manager, at (309) 654-2241, extension 3609.
Respectfully,
_l6e/
L. W. Pearce -
L Site Vice President Quad Cities Station 1
- Attachment (A), " Response to Notice of Violation" Attachment (B)," Plan to Address Reactor Vessel Head Stud Fatigue Usage Factor Concern" 4
1 n
cc:
A. B. Beach, Regional Administrator, Region Ill
. 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, Regulatory Affairs Manager, Dresden INPO Records Center.
Office of Nuclear Facility Safety, IDNS DCD License (both electronic and hard copies)
M. E. Wagner, Licensing, Comed SVP Letter File
[
t
. - - - -.., _ - - - - ~..,....,,.,.,..., _..
-..-,-m,.,-,.mc, m...-.--
....- m-..
A*ITACIIMENT A RESPONSE TO NOTICE OF VIOLATION SVP-97-280 (Page1of1)
NOTICE OF VIOLATION (50-254(265)/97018-03) 10 CFR 50, Appendix B Criterion XVI requires in part that measures shall be established to assure that conditions edverse to quality, such as failures, deficiencies, and nonconformances are promptly identified and corrected.
Contrary to the above, on September 25,1997, se inspector identified that the licensee had failed to implement prompt corrective 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 failure 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 IHS1 process.
CORRECTIVE STEPS TAKEN AND RESULTS ACilIEVED To correct the violation, Reference (c) was submitted formally docketing Comed's plan to implement the Category D inspection schedule for Unit 1 GL 88-01 Category C welds which were stress improved with the 111S1 process as discussed in Reference (b).
CORRECTIVE STEPS TAKEN TO AVOID FURTIIER VIOLATIONS Inservice Inspection administrative procedure QCTP 0410-01 will be revised to include a requirement to reclassify welds based on results of examinetions within 90 days of startup following the refuel outage when examinations were performed (e.g. to coincide with issuance of the 90 Day Summary Report). 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 ACIIIEVED Full compliance was achieved on November 20,1997 when Reference (c) was docketed.
l
O A'ITACIIMENT B PLAN TO ADDRESS RPV STUD FATIGUE USAGE FACTOR CONCERN SVP-97-280 (Page l of t)
The NRC 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 Qurd Cities Station Units I 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 1 and 2 are scheduled to continue operation into 1998, and these evaluation actior.s 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 dctermine the accuracy of the 1990 prediction of the studs reaching a CUF of 1.0 in 1998. Tb: original evaluation was based on predicted cycles.
This preliminary evaluation is bued on the actual cycles experienced as of October 23,1997. Then, using actual cycles, averaged over the last five years, predict when a CUF of 1.0 will be attained.
The results of the preliminary evaluation conservatively determined that the studs will not exwed a CUF of 1.0 during the next two (2) years for both Quad Cities Unit I and 2.
Therefore, the RPV studs are predicted to reach a CUF of 1.0 no earlier than the year 2000.
The following actions are required to resolve this issue:
Finalize 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 by December 31,1997.
Based on the above results, prepare and submit a revision to the UFSAR to accurately reflect the actions Comed is taking to assure the continued integrity of the RPV closure studs. A revision to the UFS AR will be performed in accordance with Quad's current program. In conjunction, submit a plan detailing the necessaiy long term actions to the NRC for review. These 1.ctions will be tracked under NTS# 2541009701804.03 and completed by January 30,1998 l
---_-_-_--_ - _