ML19317F529
| ML19317F529 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 08/23/1978 |
| From: | Roe L TOLEDO EDISON CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8001150843 | |
| Download: ML19317F529 (4) | |
Text
~
g a9/78~
g REGULATORY INFORMATION DISTRIDUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-346 REC: STOLZ J F ORG: ROE L E DOCDATE: 08/23/78 NRC TOLEDO EDISON DATE RCVD: 08/28/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 1 ENCL 0 FURNICHING APPLICANT"S REVISED PLANS FOR THE LOSS OF OFFSITE PWR TEST TO BE PERFORMED AT SUBJECT FACILITY, UNIT 1.
PLANT NAME: DAVIS BESSE - UNIT 1 REVIEWER INITIAL:
XJM DISTRIBUTOR INITIAL: 4._
- DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ******************
NOTES.
1.
SEND ALL AMENDMENTS TO J.
ROE PSAR/FSAR AMDTS AND RELATED CORESPONDENCE (DISTRIDUTION CODE D001)
FOR ACTION:
ASST DIR VASSALLO**LTR ONLY(1)
GR CHIEF LWR #1 BC**LTR ONLY(1)
PROJ MQ,R ENOLE**LTR ONLY(1)
LIC ASST LWR #1 LA**LTR ONLY(1)
INTERNAL:
G FIL LTR ONLY(1)
NRC PDR**LTR ONLY(1)
A
.x cw*LTR ONLY(2)
OELD**LTR ONLY(1)
OPERATOR LIC ER**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 ONL'!(1)
STRUCTURAL ENG BR**LTR ONLY(1)
MATERIAL ENO BR**LTR ONLY(2)
AD FOR REAC SFTY**LTR ONLY(1)
REACTOR SYSTEMS GR**LTR ONLY(1) ANALYSIS BR**LTR ONLY(1)
CORE PERFORMANCE BR**LTR ONLY(1 AD FOR PLANT GYSTEMS**LTR ONLY(
AUXILIARY SYS CR**LTR ONLY(1)
CONTAINMENT SYSTEMS **LTR ONLY(1 I & C SYSTEMS ER**LTR ONLY(1)
POWER SYS ER**LTR ONLY(1)
AD FOR SITE TECH **LTR ONLY(5)
AD FOR SITE ANLYS**LTR ONLY(1)
ACCIDENT ANALYSIS **LTR ONLY(1)
EFFLUENT TREAT SYS**LTR ONLY(1)
RAD ASSESSMENT BR**LTR ONLY(1)
KIRKWOOD**LTR ONLY(1)
GEOSCIENCES BR**LTR ONLY(1)
EH5e M M OT epGwerrw(, St.
EXTERNAL:
LPDR'S gg ppm gg LIk-PT. CLINTON, OH**LTR ONLY(1)
TERA **LTR ONLY(1)
OL A# I #VS #e NSIC**LTR ONLY(1)
EE8 ACRS CAT B**LTR ONLY(16) goecurre j
DISTRIBUTION:
LTR 58 ENCL 0 CONTROL NER:
Imm a c.w32 SIZE: SP jQg f cooo*******************************
THE END
- **++-
8001150 h 3
~
TOLEDO
%sm EDISON August 23, 1978 LCBNELL E. ADE v.c. pr...o F.c.uc.
c. oo-..
(4191 259 "242 Docket No. 50-346 License No. NPF-3 Serial No. 454 Director of Nuclear Reactor Regulation Attention:
Mr. John F. Stolz, Chief Light Water Reactors Branch No. 1 Division of Project Management United States Nuclear Regulatory Commission Washington, D.C.
20535
Dear Mr. Stolz:
This letter provides our revised plans for the loss of offsite power test to be performed at Davis-Besse Nuclear Power Station Unit No. 1.
We agreed to provide this information during our meeting on this subject with the NRC staff on August 1, 1978. This letter supersedes the informa-tion provided by my letter on this subject dated July 24, 1978, Serial No. 452. We plan to conduct this test in approximately 50 days. We therefore request your assistance in the expeditious resolution of any comments the NRC staf f may have on our plans.
The purpose of the loss of offsite power test is to demonstrate that the dynamic response (especially the removal of decay heat from the reactor core) of the plant is in accordance with predictions for a simulated condition of loss of turbine-generator coincident with a loss of offsite power. The test will be run with reactor power at about 15% with the turbine-generator en turning gear. The following is an outline of our test method, along with the basis for our position (see FSAR figure 8-4A):
1.
The auxiliary steam header is being supplied by the main steam reducer. The gland steam system is in service and being supplied by the main steam lines.
2.
Resin charges have been dumped from all except one condensate polishing demineralizer, which is still in service.
M2 ff?O i
- [p _
THE TOLEDO ECISCN COMPANY EDtSCN PLAZA 300 MADISCN AVENUE TOLEDO. CHIO 43652
,f
- diktY
~
^
m 3.
One makeup pump, one service water pump, and one component cooling water pump are in service and supplying cooling water and seal injection water to the reactor coolant pump (RCP) seals. This is a design requirement to prevent damage to the RCP seals.
4.
Diesel generator 1-1 is in operation and not synchronized onto essential bus C1.
Breaker AC110 will be opened, isolating bus C1 from 13.8 KV bus A.
After diesel generator 1 has picked up the load on bus C1, makeup pump 1-1 (on bus Cl) will be started.
The running makeup pump in Item 3 above will be stopped.
5.
The loss of offsite power will be initiated by simultaneously opening breakers EX01A and RX02B. This will isolate the 13.8 KV bus A from startup transformer 01 and bus B from startup transformer 02.
This action will also trip all four reactor coolant pumps. This action should result in a reactor protection system actuation, and a steam and feedwater rupture control system actuation (resulting in auxiliary feedwater flow to both steam generators).
6.
The shif t of operators will implement the station blackout procedure.
7.
Fifteen minutes after the loss of power, A bus will be re-energized. This will permit starting a control rod drive booster pump to provide cooling water to the control rod drives. Verification will be made that the breakers for the following equipment are open:
Condensate Pumps 1-1 and 1-2 Cooling Tower Makeup Pump 1-1 Turbine Plant Cooling Water Pumps 1-1 and 1-3 Heater Drain Pump 1-1 Switchyard Feeder 1 Lighting Substation Transformer CFS Dilution Pump C2 bus will be re-energized. C1 and C2 buses will be synchron-ized, and breaker AC 110 closed.
8.
An operator located near the condenser will break vacuum once gland steam is lost.
4 9.
Diesel generator 1 will be shut down. Makeup pump 1-2 will be started and powered by diesel generator 2.
Makeup pump 1-1 will be stopped. Makeup pump 1-2 will now be running along with the associated service water pump and component cooling water pump on bus D1 to protect the RCP seals. Breaker AC110 will be opened, isolating bus Cl from bus C2.
Breaker RX01A will ba reopened, de-energizing A bus.
t
.m m
~
. 10.
After a fifteen minute period of maintaining plant conditions in accordance with the station blackout procedure, plant loads may be re-energized from the startup transformers.
In accordance w".th technical specification 3.4.1, at least one reactor l
coolant pump will be started within one hour after the trip (Item 5 above).
j 1
The acceptance criteria for the test are that stable conditions are maintained throughout the test and no technical specification safety limits are exceeded.
We request that you inform us in writing of your approval of our plans for the loss of offsite power test (TP 800.26).
Very truly yours, 77 M l/} f., ~'
,g
/
Lowell E. Roe db c/12-14 s
w,
---i-r w
-- <