ML19317F566
| ML19317F566 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 07/24/1978 |
| From: | Roe L TOLEDO EDISON CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8001150887 | |
| Download: ML19317F566 (4) | |
Text
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07 0*
Y REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-346 REC: STOLZ J F ORG: ROE L E DOCDATE: 07/24/78 NRC TOLEDO EDISON DATE RCVD: 08/01/7S DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 1 ENCL 0 FURT4ISHING APPLICANT"S PLANS FOR THE LOSS OF OFFSITE PWR TEST TO BE PERFORMED
.AT SUBJECT FACILITY.
FLANT NAME: DAVIS EESSE - UNIT 1 REVIEWER INITIAL:
XJM DISTRIBUTOR INITI AL:
- o************** DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ****+++***********
NOTES:
L SEND ALL AMENDMENTS TO J.
ROE PSAR/FSAR AMDTS AND RELATED CORESPONDENCE (DISTRIBUTION CODE BOO 1)
FOR ACTION:
ASST DIR VASSALLO**LTR ONLY(1)
BR CHIEF LWR #1 BC**LTR ONLY(1)
PROJ MGR ENGLE**LTR ONLY(1)
LIC ASST LWR #1 LA**LTR ONLY(1)
INTERNAL:
REG FILE *1 R ONLY(1)
NRC PDR**LTR ONLY(1)
T & E**LF NLY(2)
OELD**LTR ONLY(1)
OPERATOR LIC BR**LTR ONLY(1)
EMERGENCY PLAN BR**LTR ONLY(1)
QAB**LTR ONLY(1)
DIRECTOR NRR**LTR ONLY(1)
MIPC**LTR ONLY(1)
AD FOR ENG**LTR ONLY(1)
MECH ENG BR**LTR ONLY(1)
STRUCTURAL ENG BR**LTR CNLY(1)
MATERIAL ENG BR**LTR ONLY(2)
AD FOR REAC SFTY**LTR ONLY(1)
REACTOR SYSTEMS BR**LTR ONLY(1) ANALYSIS BR**LTR ONLY(1)
CORE PERFORMANCE BR**LTR ONLY(1 AD FOR PLANT SYSTEMS **LTR ONLY(
AUXILIARY SYS BR**LTR ONLY(1)
CONTAINMENT SYSTEMS **LTR ONLY(1 I & C SYSTEMS BR**LTR ONLY(1)
POWER SYS BR**LTR ONLY(1)
AD FOR SITE TECH **LTR ONLY(5)
AD FOR SITE ANLY$**LTR ONLY(1)
ACCIDENT ANALYSIC**LTR ONLY(1)
EFFLUENT TREAT SYS**LTR ONLY(1)
RAD ASSESSMENT BR**LTR ONLY(1)
KIRKWOOD**LTR CNLY(1)
GEOSCIENCES BR**LTR ONLY(1) 4A twER.
EXTERNAL:
LPDR'S PT. CLINTON. OH**LTR ONLY(1)
Ab coe. Sus c-9Al TERA **LTR ONLY(1)
E9C,W err uca ER,,
NGIC**LTR ONLY(1) i ACRS CAT B**LTR ONLY(16)
R.AWT 6<'
bR-EEI5 IFou N DISTRIBUTION:
LTR ENCL 0 CONTROL NBR:
CISC O 33 SIZE: GP occoo******************************
THE END 80012so 3 7 g
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July 24, 1978 Docket No. 50-346 luLE00
%mm EDISON License No. NPF-3 LOWELL E. ROE Serial No. 452 v.c. n...
.et F.C:ht..S C.wetC9m.At (419) 259-5242 Director of Nuclear Reactor Regulation Attention:
Mr. John F. Stolz, Chief Light Water Reactors Branch #1 Division of Project Management United States Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Stolz:
This letter provides our plans for the loss of offsite power test to be performed at Davis-Besse Nuclear Power Station Unit 1.
We agreed to provide this information to you during a telephone call on July 14, 1978, with Mr. L. Engle and other members of the NRC staff. This information will also provide the basis for a meeting with the NRC staff on August 1, 1978, to resolve this matter. We plan to conduct this test in approximately 60 days.
We, therefore, request your assistance in the ex-peditious resolution of any comments the NRC staff may have on our plans.
The objective of the loss of offsite power test (our TP 800.26) is to prove that af ter a loss of offsite power, primary plant conditions are safely maintained. That is, the primary plant can control the transient and remove decay heat from the reactor core.
Our test plans are similar to the tests conducted at Crystal River (CR) and Arkansas Nuclear One.
The following is an outline of our test method, along with the basis for our position:
1.
The station is on line with power between 15 and 20%. Housepower is being supplied by the auxiliary transformer.
2.
One makeup pump, one service water pump and one component cooling water pump are in service and supplying cooling water to the reactor coolant pump (RCP) seals. This is a design requirement to prevent damage to the RCP seals.
3.
Lighting substations are deenergized, resulting in a loss of lighting to all sections of the station.
4.
An essential bus (Cl) is deenergized. Diesel generator 1-1 will automa-tically start on undervoltage and supply C1 bus.
Verification will be made that a second component cooling water pump and a second service water pump automatically start. The next step is to start a second makeup pump.
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Page Two July 24, 1978 Docket No. 50-346 License No. NPF-3 Serial No. 452 5.
The auxiliary boiler is now placed in service to be ready to pick up gland steam and steam jet air ejector steam loads. This is necessary to protect the turbine from air inrush through the glands.
6.
The loss of offsite power test is initiated by simultaneously performing the following actions. All four RCP's are tripped. Essential bus D1 is deenergized. The operating main feed pump is tripped. All non-essential pressurizer heaters are turned off. Because initiation of the test should result in actuation of the reactor protection system and the steam and feed-water rupture control system (SFRCS), there will be auxiliary feedwater flow to both steam generators. The actuation of SFRCS, which is unique to Davis-Besse Unit I compared to other operating plants, will cause the main steam isolation valves to close. It is the SFRCS which effectively isolates the primary and secondary systems from each other. Therefore, the status of secondary system equipment will not interact with the primary system and affect the test results.
For additional description of the SFRCS, see Exhibit 70 (pages 49-55) of our supplement to reportable occurrence NP-32-77-16.
This supplement was transmitted by our letter dated November 14, 1977, Mr. T. D. Murray to Mr. J. G. Keppler (with copies to Dr. E. Volgenau and Mr. W. G. Mcdonald).
7.
Station blackout procedures will be used to establish stable conditions.
The acceptance criteria for the test are that stable conditions (cooling down) are maintained for at least 30 minutes and no technical specifica-tion limits are exceeded.
There are certain other loads we plan to keep energized during the test. We believe these loads are necessary to prevent probable damage to station equipment. We firmly believe these loads will have no adverse effect on meeting the objectives of the test.
These miscellaneous loads are as follows:
1.
A control rod drive cooling water booster pump (as was done at CR) will be operating to prevent overheating the control rod drive stators.
2.
Condensate demineralizer holdup pumps will be energized to avoid dumping the polisher resins.
3.
Water treatment equipment will be operated to protect the clarifiers.
4.
Heat tracing and boric acid addition tank room heaters will be energized to prevent crystalizotion of the boric acid.
5.
Circulating water pumps and condensate pumps will be operated as necessary to maintain condenser vacuum and protect the turbine glands from damage, i
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J Page Three
. July 24, 1978 r
Docket No. 50-346 License No. NPF-3 i
Serial No. 452 I
6.
Main feed pump turbine turning gears will be energized to prevent damage to this turbine.
i' 7.
An instrument air compressor will be operated as was done at CR.
We request that, following our meeting on August 1, you inform us in writing of j
your approval of our plans for the loss of offsite power test (TP 800.26).
Very truly yours, I
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