ML18030A259
| ML18030A259 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/15/1981 |
| From: | Curtis N PENNSYLVANIA POWER & LIGHT CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| PLA-727, NUDOCS 8104210340 | |
| Download: ML18030A259 (4) | |
Text
0 REGULATORY INFORMATION DISTRIBUTION 'SYSTEM (RIDS)
ACCESSION NBR: 8104210340 DOC. DATE: 81/04/15 NOTARIZED:
NO FACIL:50 387 Susquehanna Steam Electr ic Stationi Unit li Pennsyl va 50 388 Susquehanna Steam Electric Stationi Unit 2~ Pennsylva AUTH,NAIVE AUTHOR Af FILIATION CURTIS', w ~
Pennsylvania Power L Light Co REC I.P. MA,vE RE C IP I EN l' F F ILIA TI ON YOUNGBLOOOrB ~ J
~
Licensing Branch 1
SUBJECT:
Forwards addi info per THL items II,K.1 item 22 re reactor vessel makeup water supply, DISTRIBUTION CODEe 8001S COPIES RECEIVED:LTR ENCL SIZE:
r TITLE: PSAR/FSAR AHDTS and Related Corresponaence
.NOTES:Send I8,E 3 copies FSAR L all amends'end ISE 3 copies FSAR 8'll amends.
DOCKET ¹ 0500 387 00 05000387 05'0003'88 r1EC IP I Eh T IO CODE/NAME ACTION!
A/D LICKNSNG RUSHBROOKgH ~
INTERNAL: ACCI,D'VAL BR26 CHEM ENG BR 08 CORK PERF BR 10 EMERG PREP 22 GKUSC IENCES 14 HYO/GEO BR 15
- ILK, 06 LIC QUAL BH blEC H EN G BR 1 8 NRC POR 02 OP LIC BR PROC/TST REV 20 RA ESS BR22
- -l:-
01 STRUCT ENG BR25 COPIES LTTR ENCL 1
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REC IP IKNT ID CODE/NAY>K YOUNGBLOODiB STARKeR ~
04 AUX SY'S RR CONT SYS BR 09
'FF TR SYS BR12 EQUIP QUAL BR13 HU<1 FACT ENG BR I4C SYS UR 16 LIC GUID BR
'NATL ENG BR 17 QPA OELD PO'HER SYS BR 19 AA BR 21 REAC SYS BR 23 SIT ANAL BR 24 SYS INTERAC BR COPIES LTTR ENCL 1
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EXTERNAL; ACRS NSIC 27 05 ib 1b 1
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TOTAL NUMBER OF COPIES REQUIRED:
LTTR 57 ENCL 51
TWO NORTH NINTH STREET. ALLENTOWN, PA. 18101 PHONEL (215) 770-51 St NORMAN W. CURTIS Vice President-Engineering tL Construction-Nuclear 770.5381 lr ~
l Q
IL
~ pic 1It%a 55 13ttt Mr. B. J.
Youngblood Licensing Branch 81 U. S. Nuclear Regulatory Commission Washington, D.
C.
20555 Susquehanna Steam Electric Station TMI Item II.K.I ITEM 22 ER100450 Fi 1 e 841-2 PLA-727 April 15, 1981 Docket Nos.
50-387 and 50-388
Dear Mr. Youngblood:
The following additional information is provided in response to TMI items II.K,1'tem 22.
Very truly yours, N.
W. Curtis Vice President-Engineering and Construction-Nuclear cc:
R.
M. Stark QrLO 5
rjr 8Z 0.42 >03'lo PENNSYLVANIA POWER 5L LIGHT COMPANY
~Res oese If the main feedwater system is not operable, a reactor scram will be automatically initiated when reactor. water level falls to Level 3.
(540.5 inches above vessel bottom or 178.2 inches above thee top of the active fuel).
The operator can then remote manually initiate the reactor core isolation cooling system from the main control room, or the system will be automatically initiated when reactor water level decreases to Level 2
(489.5 inches above vessel bottom or 127.2 inches above the top of the active fuel) due to boil-off.
At this point, the high pressure coolant injection system will also automatically start supplying makeup water to the vessel..These systems will continue automatic injection until the reactor. water level reaches Level 8 (581.5 inches above vessel bottom or 219.2 inches above top of the active fuel), at which time the high pressure coolant injection turbine and the reactor core isolation cooling turbine are, automatically tripped.
In the nonaccident
- case, the reactor core isolation cooling system is utilized to furnish subsequent makeup water to the reactor pressure vessel.
Reactor core isolation cooling must be manually restarted (once it is tripped by a Level 8 signal) from the main control room by reopening the stop valve at the turbine inlet. If the operator fails to restart reactor core isolation cooling, the high pressure coolant injection system will restart. automatically when the level again falls to Level 2.
No manual actions are required for high pressure coolant injection to start or restart.
Reactor vessel pressure is regul.ated by the automatic or remote manual operation of the main steam relief valves which bolw down to the suppression pool.
To remove decay heat, assuming that the main condenser is not available, the steam condensing mode of the residual heat removal system is initiated by the operator.
This involves remote manual aligment of the residual heat removal system valves.
If the steam condensing mode is unavailable for any reason, the main steam relief valves can be manually actuated from the control room.
Remote manual alignment of the residual heat removal system into the suppression pool cooling mode is then required for suppression pool heat removal.
Makeup water to the vessel is still supplied by the reactor core isolation cooling system under manual control.
For the accident case with the reactor pressure vessel at high pressure, the high pressure coolant injection system is utilized to automatically provide the required makeup flow.
No manual operations are required since the high pressure coolant injection system will cycle on and off automatically as water level reaches Level 2 and Level 8, respectively.
If the high pr'essure coolant injection system fails under. these conditions, the operator can manually depressurize the reactor vessel using the automatic depressurization system to permit the low pressure emergency core cooling systems to provide makeup coolant.
Automatic depressurization will occur if all of the following signals are present:
high drywell pressure 1.69 psig, Level 3 water Level permissive, Level 1 water level
,(398.5 inches above vessel bottom or 36.2 inches above the top of the active fuel),'ressure. in at least one, low pressure injection system and the runout of a 120 second timer (set at 105,seconds) which starts with the coincidence of the other four signals.