ML20101A128
| ML20101A128 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/13/1992 |
| From: | Broughton T GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20101A125 | List: |
| References | |
| NUDOCS 9204200229 | |
| Download: ML20101A128 (7) | |
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METROPOLITAN EDIS0N COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION, UNIT 1 Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request No.193, Revision 1 Revision 1 of 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:
Ik Vice President a3B Director, THI-l Sworn and Subscribed to before me this 13th day of _ April
, 1992, Vf)dIY TINY ~klU;,
7 Notary Public v
NantiSed NIT DM Couniv My conmu[nnbim Aug.21.1w3 Meta Pmshaia AmorWon d Natanna 9204200229 920413 PDR ADOOK 05000289 P
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4 UNITED STATES OF AMERICA HUCLE\\R REGULATORY COMMISSION l
IN THE MATTER OF DOCKET NO. 50-289 GPU NUCLEAR CORPORATION LICENSE NO. DPR-50 l
CERTIFICATE Of SERVIC_E 1
This is to certify that a copy of Revision No. I of Technical Specification Change Request No.193 to Appendix A of the Operating License for Three Mile Island Nuclear Station 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:
4 Mr. Jay H.-Kopp, Chairran Mr. Russell L. -Sheaffer, Chairman Board of Supervisors of Board of County Commissioners Londonderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Courthouse Middletown, PA 17057 Harrisburg, PA 17120 Mr. William P. Dornsife, Director PA. Dept. of Environmental Resources Bureau of Radiation Protection L
P.O. Box 2063 Harrisburg, PA 17120 GPU NUCLEAR CORPORATION l
BY:
Vice Presiden L & Director, TMI-l DATE:
April 13, 1992
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- IEAniGl_hE.1 fi c a t LQIL.0AasthmtealtiL._1M GPU Nu: lear requests that the following revisions be made to the TMI-l Technical Specification:
Remove pages 51, 4477, 4 78, 4-79, 4-80 and 4-81.
Add pages vi,- 4-77,-4-77a, 4-78, 4-79, 4-80, 4-80a and 4-81.
Eliminate pages 4-82, 4-83, 4-84 and 4-85.
GPU Nuclear requests that the following revision be made to the Facility Operating License:
Replace Page 6.
Eliminate Page '7.
II.
Reason for Chance This change is requested to revise the inservice inspection program i
for_0nce-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 during.each refueling outage, significantly increasing the level of monitoring of the general condition of the steam generator by detecting the onset of new or recurring damage mechanisms.
Expansion j
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 primarily on technical Judgement rather 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 ind 5 relate to past events, and therefore, may be deleted. Also, this change deletes reference to. a temporary change to License Condition 2(C)(8)(2) to increase the OTSG primary-to-secondary leak rate limit from 0.1 to 0.2 gallons per minute above baseline through September 27, 1991.
The changes to the current Technical Specification (TS) pages are summarized below; iist of Tables was revised to delete reference to Tables 4.19.1 and 4.19.2.
TS 4.19 was revised to delete refererste to the term " augmented" in the-paragraph titled " specification."
TS 4.19.1.a was revised to delete the reference to Table 4.19.1 and specifying that both steam gener-ators are to be inspected.
TS 4.19.2 was revised to rerlect the inservice inspection program, including sample size, tube selection criteria and expansion of sample size.
TS 4.19.3.a was 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.,
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fM nga for Chance (Cont'd)
J11]L3J was revised to eliminate the inspection frequency requirement assccia',cd with a 0-3 inspection result at a 40-month inspecticn interval, and to delete referene.e +.o Table 4.19.2.
IS_blL.3d was inccrperated into proposed TS 4.19.3.b and was also modified to reflect inspection sample sizes and expansion criteria for the ronditions ident' fied thei aln.
JfuJLLM was incorporated into the proposed TS 4.19.2.2.4 and 4
4.19.3.b.l.
J1.iJ9.4_.M was revised for clarity.
JJ A.19.4.aJ was revised to reflect the proposed Technical Specification 4.19.2.2.4.
I11R.4 M was added to oefine initial inspection results category C-3.
J.S_4.19.4.b was revised to delete the reference to Table 4.19.2.
15.4.lt.Sab Item 2 was revised for clarity.
IS 4,10.5.b ltem 4 was added to require that the basis for the determination of expansion of sampling is reprted with the inspection results.
III.
iqfaty Evqluation Current Technical Specifications require a W. sample of tubes to be inspected in each Once Through Stear Geneiater (OTSG) during each refueling outage.
Escalatior. is statistically based ar.d determined by criteria for allowable numbers of denraded had defective tubes.
The e
proposed change requires the telectice end inspection of a 20% sample representative of the entire in-service tube population in each UTSG 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 1
determined by engineering judgment.
The proposed inspection progran improves monitoring by increasing the initial sample size from 3 to 20 percent. The prngram increases the probability of detection of defective or degraded tubes.
Increasing the probability of detection should therefore reduce the probability of tube leakage.
In accordance with the current specification, tubes identified previously as degraded will continue to be inspected in subsequent inspections to monitor any degradation growth.
Upon identification of a tube centaining a defect or a tube with activo degradation, estalation will be based on the licensec's judgement, but will include at least two (2) tubes in all applicable directions.
Additionally, if the initial inspection results are category C-3 and are not conffned to a specific region or population of tubas, the inspection will be expanded to 100% of the remaining inservice tubes in the affected stecm generator. This methodology employs engineering Judgement and better use of resources as_ opposed
- to the current blind statistical expar.slon.
For defects considered indicative of known: damage mechanisms (based en experience in the THI-1 steam generators or industry experience), expansion will be based on_ engineering judgement to bound'the problem.
The 20% sample size and 100% inspection over five inspectior intervals will provide L
sufficient basis to identify known damage mechanisms, and determine the bounds of tha problem. Therefore, a blind statistical expansion is nct warrantea.
IV, No Sionifiqant ihzards Consideration GPU Nuclear has determined that the 1SCR and Licensa Amendment request poses no significant hazards as defined in 10 CFR 50.92 in that aperation of TML-1 in accordance with the proposed amenoment will not:
L 1.
Involve a significant increate in the probability or censequences of an accident previously evaluated.
Increasing the number of o
tubes inspected so that 100% inspection of OTSG tubes occurs at least once every five (5) refueling outages, which results in increased awareness of the overall condition of the OTSGs coupled with enhanced implementation of appropriate action, as applicable, will not increase, and may reduce, the probability or consequence of an accident prwiously evaluated.
2.
Create the poisibility of a new or different kind of accident from any accident previously evaluated.
This activity primarily changes the quantity of 0TSG tubes tested during cold shutdown periods, using standard industry accepted technology.
If new OTSG tube damage mechanisms occur, it should be more readily detected by increased inspection of all in-service tubes over five (5)
E inspection intervals.
3.
Involve a significant reduction in a margin of safety. The L
current method calls for inspccting fewer OTSG tubes and does not i
guarantee 100% inspection cf all tubes. The propcsed method will lead to more tubes being inspected each outage and 100% of all tubes inspected over five (5) refueling outages. Thereforc, the i
knowledge of the overall condition of the tubes will be improved E
and appropriate action taken, if needed, providing reasonable L
assurance that the margin of safety is not reduced.
In addition, the Commission has provided guidelines pertaining to the application of the three (3) standards by listing specific examples in 48 FR 14870. 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 amendent involves no significant hazards considerations.
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4-V.
Imolementation
-It is requested that the amendment authorizing this TSCR be iss'ued by Decetnber 31, 1992 and be ef fective upon issuance so that GPU Nuclear (TMI-1) may implement the changes for the Cycle 10 Refueling (10R)
Outage..If the amendment ~is not issued by December 31, 1992, an of fective date follcwing 10R is. requested.
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. (8)
Repaired _1 team Generators In order to confirm the leak-tight integrity of the Reactor Coolant System, including the steam generators, operation of 1
the facility shall be in accordance with the following:
a 1.
GPU Nuclear Corporation shall confirm baseline i
primary-to-secondary leakage rate established during the steam generator hot test program.
If leakage exceeds the baseline leakage rate by more than 0.1 gpm*, the facility shall be shut down and leak tested.
If any increased leakage above baseline is due to defects in the tube free span, the leaking tube (s) shall be removed from service.
The baseline leakage shall be re-established, provided that the leakage limit of Technical Specifici. tion 3.1.6.3 is not exceeded.
(9)
Lona Ranae Plannina Proaram The " Plan for the Long Range Planning Program for the Three l-Hile Island Nuclear Station - Unit 1" (the Plan) submitted by GPUN letter C311-88-2030 dated March 16, 1988 is approved.
a.
The Plan shall be followed by the licensee from and after May 27, 1988.
b.
The. Category A schedule shall not be changed without prior approval from the NRC. Categories B and C schedules may be changed without prior coproval by NRC.
- If leakage exceeds the baseline leakage rate by more than 0.2 gpm during the remainder of the Cycle 8 operation, the facility shall be shutdown and leak tested. Operation at leakage rates of up to 0.2 gpm above the baseline leakage rate shall be acceptable l
during the remainder of Cycle 8 operation. After the 9R refueling _ outage, the leakage limit and accompanying shutdown L
requirements revert to 0.1 gpm above the baseline leakage rate.
This license is effective as of the date of issuance and shall expire at midnight, April 19, 2014.
FOR THE ATOMIC ENERGY COMMISSION l
Original Signed by A. Giambusso l-A. Giambusso, Deputy Director L.
for Reactor Projects Directorate of Licensing
Attachment:
Appendix A Technical Specifications Date of Issuance: April 19, 1974
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