ML17037B597
| ML17037B597 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 03/02/1978 |
| From: | Rhode G Niagara Mohawk Power Corp |
| To: | Lear G Office of Nuclear Reactor Regulation |
| References | |
| Download: ML17037B597 (4) | |
Text
REGULATORY INFQRMATION DISTRIBUTION SYSTEM (RIDS
>'ISTRIBUTION FQR INCOMING MATERIAL SO-220 REC:
LEAR 6 E
NRC ORG:
RHODE G
K NIAGARA MOHAWK PWR DOCDATE: 03/02/78 DATE RCVD: 03/06/78 DOCTYPE:
LETTER NOTARIZED:
NQ COPIES RECEIVED
SUBJECT:
LTR 1'NCL'0 FURNISHING INFO CONCERNING AUTOMATIC FEEDWATER PUMP TRIP ON HIGH REACTOR VESSEL WATER LEVEL IN REPSONSE TO NRC LTR DTD 02/01/78.
PLANT NAME: NINE MILE PT UNIT 1
REVIEWER INITIAL:
XEF DISTRIBUTOR INITIAL:
DISTRIBUTION QF THIS MATERIAL IS AS FOLLOWS GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.
(DISTRIBUTION CODE A001>
FQR ACTION:
INTERNAL:
EXTERNAL:
~EA~hT.
ONLY(
RE6~
Y I
8( E+4LTR ONLY(2)
HANAUER+wLTR ONLY(1)
EISENHUT++I TR ONLY(1)
BAER++LTR ONLY(i>
GRIMES+4LTR ONLY< 1)
MCGOUGH++LTR ONLY(i>
LPDR'S OSWEGO'Y44~LTR ONLY(i)
TIC+~LTR QNLY(i>
NSIC4+LTR ONLY< 1)
ACRS CAT 3++LTR ONLY(ih)
NRC PDR++LTR ONLY(1)
OELD++LTR ONLY<i)
CHECK++LTR ONLY(1)
SHAO44LTR ONLY<i)
BUTLER++LTR ONLY(l>
J CQLLINS+4LTR ONLY<1)
DISTRIBUTION:
LTR 40 ENCL 0 SIZE:
1P CONTROL NBR:
780650169
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NIAGARAMOHAWKPOWER CORPORATION/300 ERI
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'L ARO EST ~ SYRACUSE, N.Y, 13202/TELEPHONE (315) 474-1511 March 2; 1978 Director of Nuclear Reactor Regulation Attn:
Mr. George Lear, Chief Operating Reactors Branch f13 U.
S. Nuclear Regulatory Commission Washington, D.
C.
20555 Re:
Nine Mile Point Unit 1 Docket No. 50-220 DPR-63 3
PE +
hf llew g i%INIi~II IN'/5I~q I-IISage.
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Gentlemen:
Your letter of February 1, 1978 requested information as to whether or not we plan to install an automatic feedwater pump trip on high reactor vessel water level.
At Nine Mile Point Unit 1 there are no safety or safety/relief valves located on the main steam lines which could be damaged by high water level conditions.
Safety valves are located on the reactor vessel head; therefore, this safety function is maintained.
Relief valves are located on the main steam lines.
The discharge from these valves is routed directly to the suppression pool.
- Thus, no damage would result to any equipment located inside of the primary containment should these valves actuate during a high water level condition.
The feedwater system consists of three (3) strings.
One (1) string utilizes a shaft-driven pump off the turbine whereas the other two (2) strings utilize motor-driven pumps.
The motor-driven pumps are also used in the high pressure coolant injection mode.
A high reactor vessel level 'trip of the motor-driven feedwater pumps would disable this function.
For operational reasons, it may.be advantageous to trip the shaft-driven pump on high water level to reduce the possibility of damage to the relief valves on the main steam lines.
We are currently investigating methods to implement this trip.
We will notify you by April 15, 1978 as to the feasiblity of installing such a trip on the shaft-driven pump.
Very truly yours, NIAGARA MOHAWK POWER CORPORATION 7PPggpi69 MGM/szd era d K. Rhode, Vice President System Project anagement g4d /
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