ML20042E996
| ML20042E996 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 05/02/1990 |
| From: | Creel G BALTIMORE GAS & ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20042E997 | List: |
| References | |
| NUDOCS 9005070080 | |
| Download: ML20042E996 (4) | |
Text
e BALTIMORE GAS AND ELECTRIC CH ARLES CENTER. P. O. BOX 1476. BALTIMORE. MARYLAND 21203 v$ci$.
, 7 Ma 2,1990 Nvtat am reetmov taco tec-aats U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
Document Control Desk SUlijECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & $0-318 Reauest For Amendment
REFERENCES:
(a) Letter from J. A. Tiernan (BG&E) to Mr. Ashok C. Thadani (NRC),
dated July 31, 1986, Request For Amendment (b) Letter from S. A. McNeil (NRC) to J. A. Tiernan (BG&E), dated December 19, 1986, Amendment Nos.125 and 106 to Calvert Cliffs Nuclear Power Plant Operating License Gentlemen:
The Baltimore Gas and Electric Company (BG&E) hereby requests an Amendment to its Operating License Nos. DPR-53 and DPR-69 for Calvert Cliffs Unit Nos. 1 &
2, respectively, with the submittal of the proposed change to the Technical Specifications.
DISCUSSION Technical Specification 3/4 4.I0 (Units I and 2), Structural Integrity, states. that
"... cach Reactor Coolant Pump flywheel shall be inspected per the recommendations of Regulatory Position C.4 b of Regulatory Guide 1.14, Revision 1. August 1975." Itern C 4.b.(2) states that inservice inspection should be performed for each flywheel as follows:
'A surface examination of all exposed surfaces and complete ultrasonic volumetric-examination at approximately 10-year intervals during the plant shutdown i
coinciding with the inservice inspection schedule as required by Section XI of i
the ASME Code."
j in Reference (b) the Nuclear Regulatory Commission (NRC) issued a license amendment-modifying the Unit I and 2 Technical Specification Surveillance Requirement 4.4.10.1.1 to link the completion of the reactor coolant pump (RCP) flywheel inspections to our RCP motor overhaul program. The justification for that amendment included the fact that the two-piece bolted flywheel design used at Calvert Cliffs makes in-place ultrasonic examination difficult to perform.
Therefore, the detailed level of
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'Page 2 inspection provided by tying the flywheel examinations to the RCP motor overhaul program are considered better than for a conventional in place ultrasonic examination, and also maximizes the utilization of resources dedicated to RCP maintenance.
Accordingly, we have been performing the flywheel examinations as each RCP motor is removed for overhaul. Six of the eight (four per unit) RCP motors at Calvert Cliffs have been overhauled and inspected. No recordable flaw indications were found in these six flywheels. The only remaining RCP's requiring motor overhaul and flywheel inspection are RCP ll A for Unit I and RCP 21 A for Unit 2.
The original schedules as provided in Reference (a) called for completion of the RCP motor overhaul program and flywheel inspections to coincide with the completion of Unit 1 Refueling Outage (RFO) wl0 (June 1990) and Unit 2 RFO #9 (June 1991). The dates for these refueling outages have been revised as a result of an extended shutdown of both units since the first half of 1989 to accomplish certain unrelated hardware evaluations, repairs and various administrative actions. The new schedules for Unit i RFO #10 and Unit 2 RFO w9 are fall 1991 and spring 1992, respectively, based on a i
Unit I startup in July 1990 and a Unit 2 startup in October 1990.
4 The requested change to the Technical Specifications would modify Surveillance Requirement 4.4.10.1.1 by revising the existing footnotes (i.e.,
pages 3/4 4-28, and 4 29) to replace the June 1990 and 1991 dates with a reference to the applicable Unit I and Unit 2 refueling outages, in summary, while BG&E still plans to complete the RCP flywheel inspections in conjunction with the RCP motor overhaul program, the schedule for the refueling outages during which these overhauls are to be performed has changed. This license amendment request would acknowledge this change in schedule, and would more accurately reflect the intent of the technical specification by associating the surveillance schedule with the appropriate refueling outage instead of an estimated calendar date for a refueling outage.
DETERMINATION OF SIGNIFICANT llAZARDS This proposed change has been evaluated against the standards in 10 CFR 50.92 and has been determined to involve no significant hazards considerations, in that operation of the facility in accordance with the proposed amendment would not:
(i) involve a significant increase in the probability or consequences of an accident previously evaluated; The results of our RCP flywheel inspections performed to date, and industry inspections in general, have been satisfactory. No significant degradation in RCP flywheel integrity is expected throughout the entire 40 year plant life cycle. These RCP flywheels have been idled for an extended interval due to our present outage.
Consequently. - even considering the additional time requested for the inspection completions, the flywheels will not have been subjected to any significant increase in wear or stress c::used by normal operation. Additionally, the detailed
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level of inspection provided by tying the flywheel examinations to the RCP motor overhaul program are considered better than for a conventional l
In-place ultrasonic examination.
Therefore, extending the initial ISI flywheel inspection interval does not involve a significant increase in the probability or consequences of an accident previously evaluated, or (ii) create the possibility of a new or different type of accident from i
any accident previously evaluated; This proposed change would result in an additional extension of approximately 18 months in the actual completion date for the BG&E RCP flywheel inspection program, llowever, the current inspection program, that is performance of the RCP flywheel inspection in conjunction with the RCP motor overhauls, was previously reviewed and accepted by the NRC in l
Reference (b) and would temain unaffected by this proposed change, Also, j
no new hardware is being added to the plant as a result of this proposed change, no existing equipment is being snodified, nor are any significantly different types of operations being introduced. Since no modifications to the intent of the Technical Specifications are being made, no new accident will be created by this proposed change, or (iii) involve a significant reduction in a margin of safety!
These RCP flywheels have been idled for an extended interval due to our present maintenance outage, Consequently, even considering the additional time requested for the inspection completions, the flywheels will not have l
1 been subjected to any significant increase in wear or stress caused by normal operation. The proposed change, therefore, does not involve a significant reduction in a margin of safety, laEETY COMMrtTEE REVIEW These proposed changes to the Technical Specifications and our determination of significant hazards have been reviewed by our Plant Operations and Off-Site ' Safety Review Committecs, and they have concluded that implementation of these changes will not result in an undue risk to the health and safety of the public.
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Document Control [ksk
,May 3,1990 Page 4 Very truly yours,
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STATE OF MARYLAND b&
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I hereby c rtif that on the $
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subsgiber, 3 Notary Public of the State of Maryland in' and for N" *9ite
, personally appeared George C. Creel, being duly sworn, anc' states that he is Vfe President of the Baltimore Gas and Electric Company, a corporation of the State of Maryland; that he provides the foregoing response for the purposes therein set forth; that the statements made are true and correct to the best of his knowledge, information, and belief; and that he was authorized to pr side the respo j on behalf of said Corporation.
WITNESS my lland and Notarial Scal:
3 y ' bublic My Commission Expires:
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GCC/CBH/bjd Attachments cc:
D. A. Brune, Esquire J. E.
Silberg, Esquire R. A.Capra, NRC D. G. Mcdonald, Jr., NRC T. T. Martin, NRC L. E. Nicholson, NRC T. Magette, DNR