ML19262A414
| ML19262A414 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/17/1976 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Arnold R METROPOLITAN EDISON CO. |
| References | |
| NUDOCS 7910290502 | |
| Download: ML19262A414 (6) | |
Text
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OISTOIBUTIO*l:
December 17, 1976 C*@
flRC PDR r, ray File L PDR W. Hazeltor.
orbed Rdg.
V. floonan V. Stello D. Davis' Docket :!c.:
50-289 K. R. Goller g, gg33gg T. J. Carter H. Silver Attorney, OELD OI&E (3)
R. Reid t'etropolitan Edison Coreany ATT'l: Mr. R. C. Arnold G. Zwetz,1g Vice President - Generation R. Ingran L. Shao P. O. Box 542 s
u Reading, Pennsylvania 19603 rnathy J. R. Buchanan Gentlemen:
ACRS (16)
By your letter dated October 29, 1976, you requested an anendment to your facility license which would pemit a site integrated reactor vessel surveillance crocram wherein future irradiation of Three Mile Island Unit tio. l'(TMI-1) vessel caterial specir. ens would be conducted in TMI-2.
In order to detemine the acceptability of your reauest we find we need the additional information listed in the enclosure.
In addition, however, we must also know if your procosed site inte-grated procran would be part of an overall inteorated pronran involving all Babcock & Wilcox (BSH) Ifcensees or if your procran will be independent of the BSU licensee procran.
Please advise us of your intentions in this recard by December 27, 1976.
If the TP'I program will be part of the overall MW licensee program, the information listed in the enclosure will be needed to detemine the acceptability of that procran.
Further, early deter-ination of the acceptability of the overall Drocran is necessary to avoid an adverse impact on the operating schmiules of certain licensees that have applied to participate in the procran. Accordincly, if the T".I. rogram will comorise an integral part of the overall 35W licensee progran, you are requested to orovide the inferration listed in the enclosure as soon as pcssible and in any event r.o later than January 3,1977. On the other hand, if the T'*I procrar is completely independent of the proorans of other B'Al licensees, and the overall integrated procran is ecually independent of the TMI pro,ran, you are reauested to subnit the information listed in the.31 closure within 30 days of receiot of this letter.
- Further, in this latter case your infomation submittal should clearly demonstrate that your proposed progran is fully justified withcut 1484 131
!#910290 S FA
. dependence on the operating schedules of or data availab 'lity
(.includino data from high copper impurity specimens) froa other MW licensees.
A related' concern is the nrogram you intend
+6 cmolcf to neet the requirements of 10 CFR 50, Apoendix G, Paragraoh V.C, when recuired.
In this recard you are also requested to submit within 45 days of receipt of this letter a description of any additional progran you plan to imolenent to satisfy the recuirements of 10 CFR 50, Aopendix G, Paragraph V.C.
Since such a program may require data from surveillance programs at several reactors, you should also addrass the appropriate questions in the Enclosure as they relate to your planned program in this area.
Sincerely, Robert N. Reid, Chief Operating Reactors Branch 84 Division of Operating Reactors
Enclosure:
Request for Additional Infomation cc: See next page Ish iORSd4:00?.
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1484 132
Metropolitan Edison Company cc:
G. F. Trowbridge, Esq.
Shaw, Pittman, Potts, & Trowbridge 1800 M Street, N. W.
Washington, D. C.
20036 GPU Service Corporation Richard W. Heward, Project Manager Thomas M. Crimmins, Jr., Safety and Licensing Manager 260 Cherry Hill Road Parsippany, New Jersey 07054 Pennsylvania Electric Company Mr. R. W. Conrad Vice President, Generation 1001 Broad Street Johnstown, Pennsylvania 15907 Mr. Weldon B. Arehart, Chairman Board of Supervisors of Londonderry Township 2148 Foxiana Road Middletown, Pennsylvania 17057 Miss Mar V. Southard, Chairman Citizens for a Safe Environntnt P. O. Box 405 Harrisburg, Pennsylvania 17108 Government Publications Section State Library of Pennsylvania Box 1601 (Education Building)
Harrisburg, Pennsylvania 17126 1484 133
REACT" VESSEL SURVEILLANCE PROGRAM REQUE,.. FOR ACDITICNAL INFORMATION 1.
Provide your contingency plans for assuring that your surveillance
' program will not be jeopardized by an extended cutage of any other reactor (s) from which you expect o receive data. What time limits will you place on the host
- reactor (s) for a given outage and justify these limits.
2.
Provide your program and schedule for installing the redesigned surveillance capsule holders in your reactor in the event this action becomes necessary.
3.
What is the schedule for withdrawal of your capsules from the host re, actor (s)? Relate the schedule to predicted trends in adjusted reference temperature and Charpy upper shelf energy.
What arrangements have been made with the owners of the host reactors to assure that this withdrawal schedule will be met.
4.
Specify the minimum and maximum radiation lead times for:
(a) surveillance specimens relative to the vessel beltline inner surface, and (b) surveillance specimens relative to the 1/4T position in vessel wall, which you will require for guest specimens exposed in the host reactor (s). Justify the values specified.
5.
Indicate the corrective action to be undertaken at the guest reactor if the limits specified in response to Question 4, above, cannot be met.
If the corrective action does not involve reactor shutdown, justify the proposed alternative.
.1484 134
- The " host reactor has the red signed surveillance specimen capsule holders for irradiation of both the " host capsules" wn"ch contain material representative of the host reactor beltline, and " guest capsules" which represent (for want of a better word) " guest reactors".
. 6.
Describe how the operating staff of the guest reactor will keep
' informed of the exposure status of the guest specimens at the host reactor (s) relative to the limits specified in response to Question 4, above.
7.
Submit amended proposed Technical Specifications that reflect the appropriate portions of your responses to Questions 3, 4, 5 and 6 above.
Similarity of Guest and Host Reactors 1.
Provide a cceprehensive tabulation for the guest reactor and each host re, actor, of the values of all parameters, including construc-tion and operating characteristics, that may affect the fracture toughness of the reactor vessel material as it is irradiated.
Discuss how all differences in t'hese parameters are accommodated in the integrated surveillance program.
Fluence Estimates 1.
Describe analyticd Mehniques that you plan to use to estimate the fluence expected at the various welds of the beltline of your vessel. How much uncertainty do you expect there tb be in the fluen e estimates?
2.
Describe any dosimetry checks that you plan to make on the analytical 1484 135 results.
3.
htat differences in neutron energy spectra and dose rate da you predict for your reactor beltline and your surveillance specimens, wherever they are to be irradiated? Cescribe the corrections, if.
any, that will be made to the predicted radiation damage at your beltline welds as a result of these differences. Possible corrections
~
3-include differences in specimen 1.rradiation temperatures, differences in neutron spectra arising from differences in reactor geccetry or a different type of fuel (e.g. mixed oxides), and differences in dose
" rate if scme test reactor data are used.
Traceability of 'delds 1.
Identify the heats of weld wire and! flux used in all beltline welds, and give specific locations where each is used.
2.
State which weld or welds is expected to be controlling with regard
~
to radiation damage and why, i.e., give expected neutron flux,
.' initial RTNDT, Charpy upper shelf energy, and chemical composition for the controlling welds.
3.
Which welds are represented in the surveillance capsules irradiated in your reactor?
4.
Which welds, if any, are represented in surveillance programs for
_ other reactors?
5.
List any test reactor programs on radiation damage in which your weld metals are represented.
6..
I.ist any other test reactor and surveillance programs in which welds that are expected to be in the same category as yours frca the stand-
. point of radiation sensitivity are represented, which you intend to utilize.
1484 136