ML20247M295
| ML20247M295 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/15/1989 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20247M294 | List: |
| References | |
| NUDOCS 8909250177 | |
| Download: ML20247M295 (6) | |
Text
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. METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION, UNIT 1 ii.
Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request No.193 This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix A to Operating License No. DPR-50 for Three Mile Island.
. Nuclear Station, Unit 1.
As a part of this request, proposed replacement pages for Appendix A are.also included.
GPU NUCLEAR CORPORATION BY:
V' ice Prdsident & Director, TM1-1
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Sworn and Subscribed to beforp me thjs - /#b day of A rrfi a /v n, 1989.
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. Notary Public Sharon R
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My Member, Penneytvane Assocmgan d Notsies l
8909250177 89o915 DR ADOCK 05000289 f
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UNITED STATES OF AMERICA 1
L NUCLEAR REGULATORY COMISSION i
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'IN THE MATTER OF' DOCKET NO. 50-289' GPU NUCLEAR CORPORATION LICENSE NO. DPR-50 i
l, CERTIFICATE OF SERVICE I
.This is to certify that a ccpy of Technical Specification. Change Request No. 193 to Appendix A of the Operating License for Three Mile Island Nuclear Station i
Unit 1, has, on the date given below, been filed with executives of Londonderry Township, Dauphin County, Pennsylvania; Dauphin County Pennsylvania; and the Pennsylvania Department of Environmental Resources, Bureau of Radiation Protection, by deposit in the United States mail, addressed as follows:
l
.Mr. Kenneth E. Witmer, Chairman Ms. Sally S. Klein, Chairman
. Board of Supervisors of Board of County Commissioners Londonderry Township of Dauphin County
'25 Roslyn Road Dauphin County Courthouse Elizabethtown, PA 17022 Harrisburg, PA 17120 j
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Mr. Thomas Gerusky, Director j
.PA. Dept. of Environmental Resources Bureau of Radiation Protection P.O. Box 2063 Harrisburg, PA 17120 GPU NUCLEAR CORPORATI N
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l BY:
Vi'ce President & Director, TMI-1 l
DATE:
September 15, 1989
f.
Technical Specification Change Request No.193 GPUN requests that the following revision be made to the TMI-1 Technical Specification:
Replace pages vi, 4-77, 4-78, 4-79, 4-80 and 4-81.
Eliminate pages 4-82, 4-83, 4-84 and 4-85.
GPUN requests that the following revision be made to the Facility Operating License:
Replace Page 6.
Eliminate Page 7.
II.
Reason for Change This change is requested to revise the inservice inspection program for Once-Through Steam Generator (OTSG) tubes. The revised inspection program is based on the Electric Power Research Institute (EPRI) Steam Generator Inspection Guidelines (Report No. EPRI-NP-6201, Revision 2). The revised program increases the OTSG tube sample size from 3% to 20% per OTSG each refueling outage, thus cetter monitoring the general condition of the steam generator by detecting the onset of new or recurring damage mechanisms.
Expansion of the initial 20% sample will be based on the location and nature of the defect discovered. The scope of the expansion will be based mura er. technical judgement than the existing statistical based requirements. The requirement that 100% of the tubes be inspected over a five refueling cycle interval has also been added.
Also included in this change is the request for revision of License Condition 2.C(8).
Items 1, 3, 4, and 5 relate to past events, therefore, these may be deleted.
The changes to the current Technical Specification pages are summarized below:
TS 4.19.1.a has been revised to delete the reference to Table 4.19.1 and specifying that both generators are to be inspected.
TS 4.19.2 has been revised to reflect the inservice inspection program, including sample size, tube selection criteria and expansion of sample size.
TS 4.19.3.a has been revised to indicate that the inspection interval will not exceed 24 months, and also to delete reference to the first (baseline) inspection which does not apply hereinafter to this TSCR.
TS 4.19.3.b has been revised to eliminate the specified sample size required, and the inspection frequency, if any of the applicable I
conditions have occurred.
TS 4.19.3.c.1 has been expanded to exclude primary-to-secondary tube leaks from previously plugged tubes in excess of the limits of TS 3.1.6.3 as a l
condition that requires the unscheduled inservice inspection of the affected steam generator (s). __ - _ _ _ _ - - _ - _ _ _.
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II. Reason for Change (Cont'd.)
TS 4.19.4.a.7 has been revised for clarity.
TS 4.19.4.a.8 has been revised to reflect the revised Tech. Spec.
reference.
TS 4.19.4.b has been revised to delete the reference to Table 4.19.2.
TS 4.19.5.b has been revised to specify that the complete results of the inspection are to be reported to the NRC within 12 months following completion. This change was approved in Tech. Spec. Amendment 129 and through administrative error was changed to the previously specified time frame of three months.
Item 4 has been added to require that the basis for the determination of expansion of samp*ing is reported with the inspection results.
TS 4.19.5.c has been deleted. Although the categories of inspection results have been eliminated, any severe tube degradation would be evaluated in accordance with 10 CFR 50.72. Also, the NRC is notified of the results of the inspection within 15 days per TS 4.19.5.a.
III. Safety Evaluation Current Technical Specifications require a 3% sample of tubes to be inspected in each Once Through Steam Generator (OTSG) each refueling outage.
Escalation is statistically based and determined by criteria for allowable numbers of degraded and defective tubes. The proposed change requires a 20% sample of tubes in each OTSG to be inspected each refueling outage such that 100% of the tubes are inspected over a five refueling cycle interval.
Escalation will be based on the nature of the defect as determined by engineering judgment.
The proposed inspection program provides better monitoring of the overall condition of the steam generators.
Increasing the initial sample size from 3 to 20 percent will increase the probability of detection of defective or degraded tubes. The increased probability of detection should therefore reduce the probability of tube leakage.
As in the current specification, tubes identified previously as degraded are to be inspected in subsequent inspections to monitar any growth of the degradation. The revised specification allows for tubes with no significant growth (less than 10% TW growth) over three successive
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inspection intervals to be returned to the total population of tubes to be inspected during nominal 20% inspections. This time period provides reasonable assurance that degradation mechanisms are not active. The tubes would be inspected at some time during the next five inspection intervals thus providing additional monitoring for any further degradation. _ _ _ _ - _ _ _ - _ - - - _ -
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'fIf. Safety Evaluation (Cont'd.)
Escalation upon identification of a defect is proposed to be based on the nature of the defect. Defects considered to be isolated occurrences will be bounded by two unplugged defect-free tubes in all applicable directions. This methodology employs engineering judgement and better use of resources as opposed to the current forced statistical expansion.
For defects considered indicative of known damage mechanism (based on experience in the other TMI-1 steam generator or industry experience),
expansion will be based on engineering judgement to bound the problem.
Known damage mechanisms should be well understood on a continuing basis by inspecting all OTSG tubes over 5 inspection intervals. Therefore a forced statistical expansion is not warranted.
IV. No Significant Hazards Consideration GPUN has determined that the TSCR and License Amendment request poses no significant hazards as defined in 10 CFR 50.92 in that operation of TMI-1 in accordance with the proposed amendment will not:
1.
Involve a significant increase in the probability or consequences of an accident previously evaluated.
Increasing the number of tubes inspected so that 100% inspection of every OT3G tube occurs at least once every 5 refueling outages and knowing their condition and implementing appropriate action, as applicable, will not increase, and may reduce the probability or consequence of an accident previously evaluated.
2.
Create the possibility of a new or different kind of accident from any accident previously evaluated. This activity primarily changes the quantity of OTSG tubes tested during cold shutdown periods, using standard industry accepted technology.
3.
Involve a significant reduction in a margin of safety. The current method calls for inspecting fewer OTSG tubes and does not guarantee 100% inspection of all tubes. The proposed method will lead to more tubes being inspected each outage and 100% of all tubes inspected over 5 refueling outages. Therefore, the overall condition of the tubes will be known and appropriate action taken, if needed, providing reasonable assurance that the margin of safety is not reduced.
In addition, the Commission has provided guidelines pertaining to the application of the three standards by listing specific examples in 48FR14870. The proposed amendment is considered to be in the same category as example (ii) of amendments that are considered not likely to involve significant hazards considerations. The proposed change imposes a more stringent surveillance requirement. Thus, operation of the facility in accordance with the proposed amendment involves no i
significant hazards considerations. 1
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41 V.
Implementation
'It.is requested that.the amendment' authorizing this TSCR.be issued by L,
December 1,-1989 and' effective upon-issuance in order that we' may be.able
.to implement the changer Sr the Cycle 8-Refueling'(8R) Outage.
If the.
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- amendment is'not issued December =1, 1989, we request that it be-effective following~BR..
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