ML20031C757
| ML20031C757 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 09/03/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Counsil W CONNECTICUT YANKEE ATOMIC POWER CO. |
| References | |
| LSO5-81-09-007, LSO5-81-9-7, NUDOCS 8110080342 | |
| Download: ML20031C757 (4) | |
Text
i, DIS 1.'IBUTION cDocket September 3,1981 NRC PDR Local PDr NSIC TERA Docket No. 50-213 ORB Reading LS05-81 007 DCrutchfield HSmith WPaulson OELD Mr. W. G. Counsil. Vice President oI&E (3)
Nuclear Engineering and Operations ACRS (10)
Connecticut Yankee Atomic Power Company SEPB Post Office Box 270 Hartford, Connecticut 06101
Dear Mr. Counsil:
We are continuing our review of the adequacy of station electric distribution system voltages for the Haddam Neck Plant and have found that additional information described in the enclosure to this letter is needed. We request your response within 45 days of your receipt of this letter.
Sincerely, Original signed by Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing
Enclosure:
Request for Additional Ini'ormation
\\*\\ N ly /
G cc w/ enclosure:
- 6 l
See next page f(,
[
.s j~,
i 1
[@, "SEP2 91981m."e w ;.,,
l 1
4 to 1
1
. DL y 0 5,
,,p omce>
..W.Pa.Ihs0n.; c.c.
..QC..
if.f.gl.c suauwe >
o4re 6. 9... 4.. 4.....)....4..
%;110080342 e10903
'PDR ADOCK 05000213 OFFICIAL RECORD COPY uscae mi-m ue nn
_ _ ___ g _ _ _
,o; Mr. W. G. Counsil September 3,1981 cc Day, Berry & Howard
~
~
Counselors at Law One Constitution Pitza Hartford, Connecticut 06103 Superintendent Haddam Neck Plant RFD #1 Post Office Box 127E East Hampton, Connecticut 06424 Mr. Richard R. Laudenat Manager, Generation Facilities Licensing
' Northeast Utilities Service Company P. O. Box 270 Hartford, Connecticut 06101 Russell Library 119 Broad Street l41ddletown, Connecticut 06457 Board of Selectmen Town Hall Haddam, Connecticut 061.63 Connecticut Energy Agency ATTN: Assistant Director Research and Policy Development Department of Planning and Energy Policy 20 Grand Street Hartford, Connecticut 06106 U. S. Environmental Protection Agency Region I Office ATTN: Regional Radiation Representative JFK Federal Building B.oston, Massachusetts 02203 L
Resident Inspector Haddam Neck Nuclear Power Station -
c/o V. S. NRC East Haddam Post Office East Haddam, Connecticut 06423'
e 4
REQUEST Fon A30!TIONAL INFon"ATION HADDAM NECK 1
ADEQUACY OF STATION ELECTRIC DISTRIBUTION SYSTEM VOLTAGES REF. 1:
5" letter (W. G. Counsil) to NRC (D. L. Zie: ann), dated November 15, 1979.
~ REF. 2:
CYAFC0 ' letter (W. G. Counsil) to NRC (D. M. Crutchfield),.
dated August 21, 1980.
. REF. 3:
CYAPCO letter (W. G. Counsil) to NRC (D. M. Crutchfield),
dated November 4, 1980.
'REF.4:
CYAPC0 letter (W. G. ' Counsil) to NRC (D. L. Ziemann),
dated March 6, 1980.
REF. 5:
CYAPC0 letter (W. G. Counsil) to NRC (D. M. Crutchfield),
dated May 12, 1981.
REF. 6:
NU letter (W. G. Counsil) to NRC (d. M. Crutchfield),
dated March 9, 1981.
I (1) Submit the setpoints for the overvoltage monitors stated in Ref. 2.
(2) Submit additional information pertaining to the specific p ant operating conditions during which the test verification was made ~
[Ref. 1).
Specifically include such information as the plant operating mode and bus loading percentages (Class lE buses should be loaded at least 30%).
(3) Ref. 4 states that circuit breaker ST6 has been per=anently removed from its cubicle per operating procedure No. 2.16-1.
Ref. 5 refers to the tripoing and locking out of breaker ST6 when degraded voltage conditions jaitiate protective actions.
Clarify the discrepancy 4.n these submittals on the status of circuit breaker ST6.
i (4) The failure of circuit breaker 389T399 (normally closed) would cause the tripping of both 115KV circuits to the onsite distribution system
[Ref. 1].
Submit any plans of action or design changes for eliminating the extent of this single failure from supplying power to the onsite distribution system.
(5) Do cases No. 16 through No. 29 of Ref. 3 include the effect of the load transferring due to the loss of a station service transformer supply and the automa" c closing of breaker 2T37 If not, a voltage analysis
~
is required for this scenario at all Class lE voltage levels.
1 l
?
o
~-
i l
(6) Provide the following Class lE equipnent ratings:
1 (a) Noninal voltage rating, maxicum, and nininum continuous rating on-the. Class lE cotor starters and contactors.
(b) Maximum and mini =un continuous rating on 120-volt Class 1E equipment and instrucents.
(7)
Subtit the voltage transient duration time when starting the steam generator fecdwater pump fcr the ucrst case conditiens (cases 15 cnd 29, see aise question (5) if. applicable).
(8) The loss-of-voltage protection sche =e has a setpoint of 2870 volts (72.8% of the 4000-volt motor rating) with a time delay of less than one second. A level 2 protection schece has been proposed [Ref. 6]
with a setpoint of 3620 volts (90.5% of the 4000-volt motor rating) with a time delay of 9 seconds.. This propose.1 calls for an alarm actuation only at the level 2 setpoint unless an S1 signal is present.
The reactor would be placed in a hot standby mode if the voltage dropped bele. 3620 volts.
From the above protection schemes and..
operating scenario, the following is noted:
(a) The Class lE equipment w 11 not be trotected fro: undervoltage l.
conditions between the 72.8% and 90.5% voltage levels unless an S1 signal is present.
(b) No definite time has been established for how long Class lE equipment would be in operation in the 72.8% to 90.5% voltage range.
(c)
Docu=entation has not been provided to verify that the Class lE equipment will not be da= aged, experience degradation, or will be able to operate satisfactorly in,the 72.8% to 90.5% range for an indefinite time.
Eased on the~above discussion, provide proposed changes to automatically protect all Class lE equipment in the 72.8% to 90.5% voltage range or provide the necessary documentation to satisfy itec (c).
I l
\\
l I
i s
e5