ML19210A088
| ML19210A088 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/27/1978 |
| From: | Herbein J METROPOLITAN EDISON CO. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| GQL-0510, GQL-510, NUDOCS 7910240809 | |
| Download: ML19210A088 (3) | |
Text
04fo+,17 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-289 REC: REID R W ORG: HERBEIN J G DOCDATE: 03/27/7S NRC METROPOL EDISON DATE PCVD: 03/31/75 DOCTYPE:
ETTER r~~
<7ED: NO
SUBJECT:
COPIES RECEIVED LTR 1 ENCL 0 FURNISHING INF9 CNCERM~4G TEED-WATER LINE BREAK ACCIDENT RESULTS FREVIOUSLY SUPMITTED AND $NTICIPATED VALUES OBTAINED BY LINEAR INTERPOLATION, IN REGARDS TO ISSUANCE C.
A*"ND 28 TO OPERATING LIC NO DPR-50.
PLANT NAME: THREE MILE ISLAND - UNIT 1 REVIEWER INITI AL:
XJM DISTRIBUTOR INITIAL:ph
- DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ******************
GENERAL DISTRIBUTION FOR AFTER ISSUONCE OF OPERATING LICENSE.
(DISTRIBUTION CODE AOO1)
REIDI*'t FOR ACTION:
B F
ONLY(7)
INTERNAL:
REG FILE **LTR ONL
/
NRC PDR**LTR ONLY(1)
.s."EVWh*6'Re9Nt? r..
OELD**LTR ONLY(1)
HANAUER**LTR ONLY(1)
CHECK **LTR ONLY(1)
EISENHUT**LTR ONLY(1)
SHAO**LTR ONLY(1)
BAER**LTR ONLY(1)
BUTLER **LTR ONLY(1)
GRIMES **LTR ONLY(1)
J COLLINS **LTR ONLY(1)
J.
MCGOUGH**LTR ONL Y( 1)
EXTERNAL:
LPDR'S HARRISBURG, PA**LTR ONLY(1)
TIC **LTR ONLY(1)
NSIC**LTR ONLY(1)
ACRS CAT B**LTR ONLY(16)
DISTRIBUTION:
LTR 40 ENCL O SIZE: 2P CONTROL NBR:
7S09S0024 THE END 1489 038 7910240b
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POST CFFICE BOX 542 READING, PENNSYLVANI A 196CJ TELEPHONE 215 - 9r3-0601 5' arch 27, 1978
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GQL 0510 Director, :Iuelear Reactor Regulation Attn:
R. W. Reid, Chief s
Operating Reactors Branch :To. k b;d] 7
.m U. S. Nuclear Regulatory Comissicn
- u. 3,
~'4/3" Washington, D. C.
20555
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Dear Sir:
Three Mile Island Nuclear Station Unit 1 (TMI-1)
Operating License No. DPR-50 Decket No. 50-289 High Pressure Trip and Pressurizer Code Safety Valve Settings Your letter of April 6,1977, issuing Amendnent No. 28 to Met-Ed Cperating License No. DPR-50 for TMI-1, approved an increase in the settings for the High Pressure Trip and Pressuri::er Code Safety Valves through Cycle 3 only.
Furthermore, you stated that to eliminate the need to address these settings separately for future cycles, Met-Ed should co=it to add the Feedvater Line Brt.ak accident to those accidents already regularly considered in connection with each reload.
It has been Met-Ed's centention that the Feedvater Line Break Analysis, showing the insensitivities to Moderator and Doppler Coefficients, vould justify the 2h05 psig High Pressure Trip Setpoint and 2500 psig Pressurizer Code Safety Valve Setting on a pernanent basis. The following Tables provide the Feed-vater Line Break Accident Results previously submitted and anticipated values obtained by linear iricerpolation.
Feedvater Line Break Accident Results (Previcusly Submitted)
High Pressure Trip Mcderator Coer. Doppler Coef.
Case Setuoint, usig 10-k Ak/k/0F 10-5 Ak/k/ F Pressure, psia 1.
Cycle 1 2355
+0.5
-1.17 2637 2.
Cycle 2 2355
-1.06
-1.h9 2633 3
Cycle 2 2h05
-1.06
-1.h9 2653 Feedwater Line Break Accident Pesults (Anticipated)*
h.
Cycle 3 2355
-0.91
-1.h7 2633.h 5
Cycle 3 2h05
-0.91
-1.h7 2655.h 6.
Cycle h 2355
-0.63
-1.a9 263h.1 7
Cycle h 2!.05
-0.63
-1.h9 2656.1
- Anticipated values using the BCC (= cst positive) Moderater and Doppler Coefficients.
Ifum039 do 89 4
e Mr. R. '4.
Reid, Chief March 27, 1978 GQL 0510 As indicated in the table, vide variations in Moderator and Deppler coefficients have no sie,.ificant effect en the pressure. This is as expected; i.e., the Feed-m vater Line Break accident occurs so rapidly that ther reefficients do not see the transient.
In view of the above, sufficient jus +.ification exists to warrant the permanent settings of 2kO5 psig and 2500 psig for the High Pressure Trip and Pressurizer Code Safety valves, respectively.
, J,S cerely,//
/
.,4
' y;
/. G. Herbein J
,/ Vice President-Generaticn JGH:RJS:cjg 1489 040