ML19210A758
| ML19210A758 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/07/1978 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Herbein J METROPOLITAN EDISON CO. |
| References | |
| NUDOCS 7910310575 | |
| Download: ML19210A758 (5) | |
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3.ISIBLBUTION:
[ Docket 3 l7/}
' NRC FOR gray file 6/
L POR ORB #4 Reading Docket Ho. 50-289_
[Gol r/TCarter
-Attorney, OELD OI&E(3)
RWReid GZwetzig ibtropolitan Edison Company ATTM: Mr. J. G. Herbein RIngram DElsenhut Vice President TAbernathy P. O. Box 542 Reading, Pennsylvania 19603 Gentlemen:
By letter dated Januan 9,1978, you requested amendment of Facility Operating License No. DPR-50 for Three Mile Island Huclear Station, Unit No.1 '(TMI-1). Your request would revise the TNI-1 technical specifications as necessary to pemit operation in Operating Cycle No. 4, Changes to your original submittal were transmitted by your letter dated April 3,1978. These changes were requested because of extended operation in the pmceding cycle occasioned by the recent national coal strike and the desire to reduce poutble quadrant flux tilt problems.
m As a result of our review of your submittals, we find we need additional infomation to continue our review. The specific infomation needed
~is set forth in the enclosure. A copy of this enclosure has also been sent to you this date by facsimile transmission. As indicated to your Mr. Ron Stevens by:the NRC Project Manager for TMI-1, the limited pmspect of authorizing your request for pcmission to operate in Cycle 4 by April 21,1978, is entirely contingent upon receipt of complete and fully responsive answers to the questions contained in the enclosure, prior to the close of business on Honday, April 10,1978.
-Sincerely, Robert W.~ Reid. Ch'tef
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Operating' Reactors Branch f4 i
e Division of Operating Reactors
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enci a u m e 1493 255 I
Request'for Additional Information
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G. F. Troubridge, Esquire Shaw, Pittman, Potts & Trowbridge 1800 M Street, it.W.
Washington, D.C.
20036 GPU Service Corporation Richard W. Heward, Project 11anager 11r. T. Gary Droughton, Safety and Licensing !!anager 260 Cherry Hill Road Parsippany, !!ew Jersey 07054 Pennsylvania Electric Coapany fir. R. U. Conrad Vice President, Generation 1001 Broad Street Johnsto. n, Pennsylvania 15907 Iliss ilary V. Southard, Chairuan Citizens for a Safe Envircraent P. O. Box 405 liarrisburg, Pennsylvania 17108 Government Publications Section State Library of Pennsylvania Box 1601 (Education Builcinq) 0h e
Harrisburg, Pennsylvania 17126 ob'tMQ D
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REQUtST FOR ADDITIONAL INF0PBATION THREE 11ILE ISLAND UNIT N0.1 DOCKET NO. 50-289 OPERATION IN CYCLE 4 (0-125t5 EFPD) 1.
Describe the changes to the CVCS necessary to use the feed-bleed mode of operation.
2.
The Tech Spec changes presented in the April 3,1978 submittal appear to be based on cross-core shuffle of the fuel even though this refueling configuration is no longer being proposed.
Describe in detail the effects of non-cross-core shuffle on the parameters contained in the January 9, 1978 submittal.
Revise or verify all tables presented in the January submittal to reflect the effect of the additional cycle 3 burnup and the non-cross-ccre shuffle.
3.
The beginning of cycle (B0C) boron concentration for cycle 4 reported in Table 1 of the April 3,1978 submittal is less than that in the FSAR.
Provide available operator response times for a boron dilution event occurring (1) during refueling, and (2) during startup, cold shutdown, hot standby, and power operation.
4.
Tech Spec change request No. 75, dated March 13, 1978, is for a change to allow a 4% uncertainty between the excore measured power and the power obtained by a plant heat balance.
In view of the assumed 2% error in measured power required to be osed in accident and transient analyses, explain how the 4%
uncertainty has been accounted for in the accident analyses and the protection system setpoints.
If the additional uncertainty in power has not been accounted for in the accident analyses, provide new analyses, including ECCS, which prope rly reflect the additional 2% uncertainty.
5.
Provide an updated power map which reflects the additional cycle 3 burnup and the non-cross-core shuffle for cycle 4.
6.
Provide or reference the bounding transient and accident analyses f
during bleed and feed operation.
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s 7.
Provide an explanation of the increase in quadrant tilt from 3.40 to 4.92% being proposed in the Technical Specifications.
What kind of a penalty is taken in the calculation of peaking factors in order to account for the allowable 4.92% tilt?
Provide P.he basis for the adequacy of this penalty.
8.
How many orifice rod assemblies will be present during cycle 4?
Where will they be located? What are the peaking factors and flow problems associated with removal of orifice rod assemblies?
9.
What is the maximum impact energy (in ft-lb) corresponding tc the alarm setpoints currently used in the Loose Parts Monitoring System? Also, briefly describe the location of the accelerometers.
10.
Provide the following infonnation regarding measurements made during cycle 3.
a) Provide a low and high power XY power map for BOC 3.
Both measured and predicted assembly powers should bt given.
b) Provide the measured and predicted B0C 3 rod bank worths, I
by bank.
c) Provide the 30C 3 measured values for critical boron concentration and moderation temperature coefficient State the power and xenon conditions under which each measuredment was taken.
d) Provide the measured and predicted ejected rod worth for B0C 3.
State'the condition under which the test was done.
- 11. The startu? Dhysics test program.jlts given in Section 9 lacks the necessary depth of discussion. A significant amount of additional detail will be reauired in order to make clear the acceptability of the methods, procedures and acceptance criteria used for the various teste.
Specifically, the fol-lowino questions are submitted on the test programs.
! 'a) Describe in detail the tests being done to check for a misloaded assembly. What assurances are there that tna cor*. is as expected before going to powers >5% rated power?
b) Describe the Drocedures for the control rod-trip test.
Include the acceptance criteria and the procedures to be followed if the accept-ance criteria are not met.
c) Provide the details of the procedures for the critical boron concen-tration tests. Discuss how corrections are made to the measured data and how the measured data is compared to the predictions.
What are the accettance criteria and what are the procedures if tne acceptance criteria are not met?
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d) Describe in detail the procedures and methods used for the temperature reactivity coefficient tests. Also provide the acceptance criteria and the procedures to be followed if the acceptance criteria are not met.
i e) Provide the details of the regulating control rod group 3
reactivity worth tests.
Give the predicted worth of each group to be measured, and the stuck rod worth and the predicted total worth for all rods. Also provide the acceptance criteria and the procedures to be followed if the acceptance criteria are not met.
f) Describe in detail the procedures for the ejected control rod reactivity worth test.
State the methods used to compare the measurements with predictions and the acceptance criteria. Also, include procedures if the acceptance criteria are not met, g) T!!I-l had a quadrant tilt at the beginning of Cycle 3.
How did this tilt change during the cycle? How was the presence of this tilt used in the predictions of the power distribu-tions for Cycle 4?
h) Provide the details of the core power distribution tests.
Describe in detail the methods used to predict the assembly by assembly power as well as the analyses of the data obtained during the measurements. What are the assembly by assembly acceptance criteria? How are tilts accounted for in the analysis of the data? If a 1/4 or 1/8 core map is the result of the measurement, what method is used to determine the assembly power for those assemblies having their symmetric assemblies instrumented? For example, are the measured assembly powers averaged, or is only one of the symmetric measurements used?
i) Provide a commitment to prepare a brief summary report of the Cycle 4 physics startup tests and to submit this report to NRC within 45 days of the completion of the startup tests.
This report should include both measured and predicted values.
If the difference between the measured and predicted values exceed the acceptance criterion, the report should discuss the adequacy of the actions taken.
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