ML19253B940
| ML19253B940 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/11/1976 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | Mcdonald W NRC OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS (MPA) |
| Shared Package | |
| ML19253B941 | List: |
| References | |
| GQL-1561, NUDOCS 7910310659 | |
| Download: ML19253B940 (3) | |
Text
NRC FORu 195 U.S. NUCLE A R R EGULATO R Y '
MISSION DOCKET NUMdE A (2 76#
3].]39 NR('. DISTRIBUTION ecR PART 50 DOCKET M ATERI AL "h'."$"g*'" REPORT TO:
FROM:
QATE OF COCUMENT
'!c tropoli tan Edison Comoan7 11/11/76 Mr.. '. C. !!CDonald Reading, Pa*
OATE RECEIVED
- !r. Robert C. Arncld 11/15/76
%ETTER CNOTORIZED PROP
' (NPUT FORM NUMBER OF COPIES RECEtVED MOR IGIN A L jig (jNg gA$$3 plE c One s'.;ned C CCP Y DESCRIPTION ENCLOSU AE LETTER TRANS TJ FOLLOWING:
MONTHLY REPORT FOR October, ll'6 PLANT & COMPONENT OPERABILITY &
AVAILABILITY. THIS REPORT TO BE USED IN PREPARING GRAY BOOK BY PLANS & OPERATIONS.
ACKNOWLEDGED PLANT NA12:
(2-P)
(3-P)
DOINOT REMOVE Three Mile Island al 1505 552 d Ar t. H FOR AC TION /INFORMATION c M ihU il/15/76 RJL K MIPC W/4 CYS FOR ACTION INTERNAL DISTRIBUTION W orc FTT b
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Director of Nuclear Reactor Regulation Attn: Mr. W. G. McDcnald, Director
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Office of Management Information
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Dear Sir:
Enclosed please find the October Operating Status Report for Three Mile Island Nuclear Station Unit 1 (TMI-1).
Recently, it was brought to our attention by the USNRC Office of Inspection h Enforcement, Regicn 1, that our TMI-l Monthly Operating Status Report forms differed to sc=e extent frc= these proposed by USNRC Regulatory Guide 1.16 Revision 4.
Besides slight editorial differences, the main dissimilarities included:
- a. Reg. Guide 1.16, Rev. h recc== ends the submittal of reactor and unit service factors in additien to the reactor and unit availability facters that were being reptrted by Met-Ed.
- b. In addition to plant shutdevns, significant dips in average pcver levels are recen= ended to be reported.
- c. The submissicn of the design electrical rating is suggested.
- d. A unit capacity factor baced en the plant's design electrical rating is recc== ended to be submitted in addition to the capacity factor based cn the maximum dependable capacity.
Starting with this report, Met-Ed is submitting the information referenced in a and b above. TMI-l was designed to operate at core power levels up to 2535 Wt which, when the 16.Wt centribution frc= the reactor coolant pumps is included, cross electrical outputs in the range of approximately 330 tc 870 We can be expected, dependin6 cn weather conditions. The design electrical rating is described as "the nc=inal net electrical output of the unit specified by the utili*.y and used for the purpose of the plant desig.."
1505 753 4l..$. () Q
Mr. W. G. McDcnald, Director GQL 1561 2
The NEC, in the absence of Met-Ed submittal cf this information in the monthly cperating status report, has been using a value of apprcximately 819 MWe (net) ss TMI-l design electrical rating. This is the result of subtracting 52 MWe (to account for plant service lead) frcs a 871 MWe (gress) value referenced on Secticn 1, page 1-1 of the TMI-l FSAR. With this data the NRC has been calculating the TMI-l capacity factors based on the design electrical rating.
However, this is not completely correct since (a) a 819 MWe (net) value was not used as the basis for TMI-l design, (nor was any other generatcr output; gross or net), (b) the plant gross output depends on prevailing ambient conditions and, (c) the plant service ic.d is not a ecnstant value, neither over the short term nor the 1cng term.
Therefore, in order to be respcnsive to the NEC concerns referenced in c and d above, we vould need a definition of design electrical rating which define how to treat specifically:
- 1) What condenser AT or metecrological conditions shall be assumed to calculate the plant gross output;
- 2) What plant service load shall be assumed; or
- 3) Shall we use the plant's su==er rating, vinter rating, or an average of the two?
In order to assure a meaningful and censistent set of NRC data, I vculd suggest that other utilities be contacted for concurrence with your final definition.
With this information we vill then be able to more closely fcllev the guidelines proposed by Reg. Guide 1.16, Rev. I Sincerely, ib Robert C. Arncld Vice President RCA:JMC:rk Encicsure ec:
Mr. J. P. O'Reilly, Direetcr Office of Inspection and Enforcement, Region i U. S. Nuclear Regulatory Cc= mission 631 Fark Avenue King of Prussia, Pennsylvania 19hC6 1505 ;54