ML20003D782
| ML20003D782 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/26/1981 |
| From: | Hukill H METROPOLITAN EDISON CO. |
| To: | Ross D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20003D781 | List: |
| References | |
| L1L-076, L1L-76, NUDOCS 8103310602 | |
| Download: ML20003D782 (5) | |
Text
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O Metropolitan Edison Company
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Post Office Box 480 a
M4ddletown. Pennsylvania 17057 Wrrter's Direct Deal Number March 26,1981
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L1L 076 Of fice of Nuclear Reactor Regulation Attn:
Denwood F. Ross, Director U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Sir:
Three Mile Island Nuclear Station, Unit 1 (DII-1)
Operating License No. DPR-50 Docket No. 50-289 Reactor Vessel Thermal Shock Report Rev. 1 Enclosed please find a copy of the same revised pages to B&W operating guidelines for small breaks (B&W 74-1122501-00) which updates our letter of February 23, 1981 (TLL 022).
REV. NO.
CHANGE SECT / PARA.
DESCRIPTION / CHANGE AUTHORIZATION 01 4.2.2 Changed to "one pump per loop" which was in the Preliminary Document but inadvertently omitted in the original issue.
4.5.1.6 Paragraph deleted.
4.5.2 Correct reference to Figure 1.
Sincerely,
. D.
.ukil Director, DII-l HDH:LWil:lma Enclosures cc:
R. W. Reid w/o Enclosures a
H. Silver w/o Enclosures pp q
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TABLE OF CONTENTS / EFFECTIVE PAGE llST
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SECTIM TITit PAGE 000. 30.
PART I OPERATING GUI:ELINES FOR SMALL EREAKS 1.0 SYMPTOMS AND INDICATIONS (IMMEDIATE I
I NDICm IONS) 4 74-1122501-00 4 -
2.0 IMMEDIATE ACTIONS 4
74-1122501-00 i
1 3.0 PREC ALTT IONS 5
74-1122301-00 6
74-1122501-00.
7 74-1122501-00 8
74-1122501-00 t
4.0
~ FOLLOWUP ACTIONS 8
74-1122501-01
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9 74-1122501-00 10 74-1122501-00 11 74-1122501-00 t
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12 74-1122501-01 i
13 74-1122501 4 0 i
14 74-!!22501-00 APPENDIX A LPI COOLING 15 74-1122501-00 16 74-1122501-00 17 74-1122501-00 f
PART II SMALL SREAK PHENOMENA - DESCRIPTION OF PLANT liEllAV10R 1.0 INTRODUCT ION 18 74-1122501-00 i
2.0 IMPACT OF RC PUMP OPERATION ON A SMALL j
LOCA 18 74-1122501-00 19 74-1122501-00 l
3.0 SMALL SREAKS WITH AUXILIARY FEEDWATER 19 74-1122501-00 20 74-1122501-00 21 74-1122501-00 22 74-1122501-00 4
4.0 SMALL BREAKS WITHOUT AUXILIARY FEEDWATER 22 74-1122501-00 i
23 74-1122501-00 24 74-1122501-00 5.0 TRANSIENTS WITH INITIAL RESPONSE SIMILAR TO A SMALL SREAK 24 74-1122501-00 j
25 74-1122501-00 6.0
' TRANSIENTS TilAT MICHT INITI ATE A 25 74-1122501-00 f
l LCCA 26 74-1122501-00 l
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- BABCOCK & WILCOX wrCitas poets Gtweea50N cmssON Nua sis TECHNICAL DOCUMENT 74-11225o1-01 3.11.1 Marmal limits and precaut ions apply for RC pump operat ion.
J.11. 2
- If the PC pumps are tripped for any reason, wal inject ion should be maintained to ensure long term seal ic.c e gr i t y.
4.0 FOLLOWUP ACTIONS 4.1 Identification and Early Cont rol 4.1.1 If HPI has initiated becaase of low pressure, control llPI in accordance with Steps 3.3 & 3.4.
4.1.2 If both liPI trains have not act uat ed on ESFAS signal, start second IU)I t rain if pos sib le.
Salance HPI fl ows.
4.1.3 If RC pressure decreases continuously, verify that core flood tanks (CFTs ) a nd low pressure injection (LPI) have actoitei as n"ded, ar.d balance LPI.
4.1.4 If cause for cooldown/depressurizat ion is de t e r.sined to be due to a non-LOCA overcooling event and the RCS is at Icast 500F subcooled then proceed to Sect ion 4.4 4.1.5 Attmpt to locat e and iso la t e le ak i f pos s ib le.
Letdown was i so la t eJ in Step 2.2.
Other isolatable leaks are PCRV (close block valve) and between valves in spray line (close spray and block valve).
4.1.6 Determine availability of reactor coolant pumps (RCPs) and main and auxiliary feedwater systms.
If feedwater is not available, go to 4.2.
If feedwater is available, go to 4.3.
4.2 Actions if Feedwater is not Available 4.2.1 Throughout the following steps maintain maximum HPI flow per Step 3.4 and restore feedwater as soon as possible.
4.2.2 If the subcooling margin is adequate and ~< cps are oper.it ing, go to one pump per loop.
If RCPs are not ope r a t i ng, go to Step 4.2.5 (01) below.
4.2.3 If RCS pressure increases, open PORV and le ave open.
NOTE:
If the PORV cannot be a c t ua t ed, the safeties will relieve pr es s ur e.
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TECHNICAL DOCUMENT 74-i n2501-01 4.4.4 Using turbine bypass valves and feedwater system, control steam generators as needed to limit plant heatup until RC pressure control can be re established with the pressurizer.
NOTE:
Cold RCS water may have been added to the pressuriser; therefore, a period of time may elapse before normal RC pressure control can be established with the pressurizer h e at e rs.
4.4.5 once pressur e cont rol is re st.61i shed, use nor.aal teatup/cooldown procedure to est ablish desired plant condi t ions.
4.5 Actions for Inadequate Core Cooling 4.5.1 Ictnediate steps for inadequate core cooling NOTE:
If RC pumps are running, do not trip pumps.
This supercedes instruct ions in Sect ion 2.1.
4.5.1.1 Verify HPI/LPI systaas are funct ioning properly with maximum flow.
Start makeup pump (s), if possible, to increase inject ion flow.
4.5.1.2 Verify steam generator level is being controlled at 95': on operate range.
C AttrION:, Reference leg boiling could give false level indication.
4.5.1.3 Depressurize operative steam generator (s) to establish a 1000F/hr decrease in secondary saturat ion temperature.
- 4. 5.1.4 Ensure core flood tank isolation valves are open.
4.5.1.5 If reactor coolant system pressure increases to 2300 PSIC open pressurizer PORV to reduce reactor coolant sys t m pressure.
Re-close PORV when RCS f alls to 100 PSIG above the secondary pressure.
Repeat if necessary.
If PORV is not ope rab le, pressurizer safety valves will relieve pressure.
- 4. 5.1. 6 Paragraph delet ed.
(01) 4.5.2 k' hen the indicated incore thermocouple temperatures or het leg RD t empe ra tur es are superheatM fo r t he ex i s t ing RCS pr es s ur e, ope ra-tor action shall be based on condit ions determined from Figure 1, (01) by a sample of the highest incore thennoccuple tersperature readings to determine the core exit thermocouple t em pe ra t ure.
NOTE:
>! ore than one thermocouple tmpe rature reading should be used (for example use the average of 5).
4.5.3 khen the incore themocouple temperature has been determined per Sect ion 4. 5. 2, go to the sect ion indicated below.
DATE:
1-15-81
METROPOLITAN EDISON COMPANY %., c-,
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$ssbject OUTGOING NRC CORRESPONDENCE Locstion
'!MI Date March 17, 1981 78 R. J. Toole - Service Bldg.
L1L 076 A:: ached is a planned response to the NRC.
Please review the attached le::er and return your comments to licensing-Uni: I within 3 vorking days of receipt of this memo.
as L.
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Earding
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Supervisor of Licensiing IMI-l LL'E:DGM:bh Atta h :
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1 P002 ORIGINAL INTER-OFFICE MEMORANDUM
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