ML20009F384
| ML20009F384 | |
| Person / Time | |
|---|---|
| Site: | Crystal River |
| Issue date: | 07/17/1981 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Hancock J FLORIDA POWER CORP. |
| References | |
| NUDOCS 8107310087 | |
| Download: ML20009F384 (2) | |
Text
.____
s O
ifguty 17 Ill01 G-n'E7DTRUT" Oft:
ilSIC ACRS-10 Cnnct nt ri' N ORB #4 Rdg Gray File
- NRC PDR-DEisenhut H0rnstein L PDR~
JStolz EBlackwood TERA PErickson ram Docket flo. 50-302 IE.3-T
't M<
,3
~
Mr. J. A. llancock
?
i
- p. %q,4gc Director, Nuclear Operations
~
6-
?
Florida Power Corporation P. O. Box 14042,11 ail Stop C-4
[~~
g,,$.
9 St. Petersburg, Florida 33733,
Dear Mr. Hancock:
SUDJECT: DEGRADED GRID VOLTAGE By letter dated April 10, 1981 we_ requested additi.onal information regarding degraded grid voltage. Discussion with Mr. D.,Hardis of your staff indi-cates that you did not receive that letter. We have, therefore, provided another copy of our April 10 request with this letter. Please provide the requested infonnation within '45 days of the date of this letter.
Sincerely, ORIGUIAL SIGIC BY JOHN F. STOLUS John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing
Enclosure:
Request for Information on Degraded Grid Voltage Dtd. 4/10/81 cc w/ enclosure:
See next page f
8107310087 810717 PDR ADOCK 05000302 p
PDR Orricap 0RB#4:D C-0RB#4:DL suaR = ) P.E..r. i.c ks. o nJ om> 7/g../81: cab 7/[...
/
- NRC FORM 318 4tos eO) NRCM O2 dO OFFICIAL RECORD COPY e - = -a2n 24
e f.
e Crystal River Unit No. 3 50-302 Florida Power Corporation cc w/ enclosure (s):
Mr. S. A. Brandimore Mr. Robert B. Bo um Vice President and General Counsel
~ Babcock & Wilcox P. O. Box 14042 Nuclear Power Generation Division St. Petersburg, Florida 33733 Suite 420, 7735 Old Georgetown Road Bethesda, Maryland 20014 Mr. Wilbur Langely, Chairman Board of County Commissioners Mr. Tom Stetka, Resident Inspector Citrus County U.S. Nuclear Regulatory Commission Iverness,- Florida 36250 Route f3, Box 717 Crystal River, Flori:fa 32629 U. S. Environmental Protection Agency Region IV Office Mr. Dan C. Poole ATTN: EIS COORDINATOR Nuclear Plant Man &ger 345 Courtland Street, N.E.
Florida Power Co.poration Atlanta, Georgia 30308 P. 0; Box 219 i
Crystal River, Florida '32629 Director, Criteria and Standards Division Office of Radiation Programs -(A.NR-460) as in o O
maau of I'.tergovernmental Relations 660 Apalachee Parkway -
Crystal River Fublic Library Tallahassee, Florida ~ 32304 668 N. H. First Avenue Crystal River, Florida 32629 Mr. J. Shreve The Public Counsel Room 4 Holland Bldg.
Tallahassee, Florida 32304
~
Administrator Department of Environmental Regulation l
' Power Plant Siting Section i
State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301
.v Attorney Gene ~ral Department of Legal Affairs The Capitol Tallahassee, Florida 32304
[
'I a
_ _,. _ _ ~ _, -.
[pS UC Io,,
i UNITED STATES g
NUCLEAR REGULATORY COMMISSION y
E WASHINGTON, D. C. 20555
.. t a
%, v.....8 April 10, 1981 Docket No. 50-302 Mr. J. A. Hancock Director, Nuclear Operations Florida Power Corporation P. O. Box 14042, Mail Stop C-4 St. Petersburg, Florida 33733
Dear Mr. Hancock:
SUBJECT:
DEGRADED GRID VOLTAGE During our review of your submittal of December 22, 1980 regarding degraded grid voltage we determined that additional information was needed. The additional information that we need is identified in Enclosure No.1.
Please respond within 45 days of the date of this letter.
Sincerely, i)
U ll.. -
Jo,hn F. Stolz, Chie erating Reactors Branch #1 Division of Licensing Enclosure :
Request for Infomation l
on Degradad Grid Voltage cc w/encicsure:
See next page v
. o. >
e V$ b' g
p i
+. <
Enclosure CRYSTAL RIVER 3 Docket No. 50-302 REQUEST FOR ADDITIONAL INFORMATION ON DEGRADED GRID PROTECTICN FOR CLASS lE POWER.SYSTEFE References a.
Florida Power Corporation (FPC) letter, P. Y. Baynard to Division of Licensing, NRC, " Adequacy of Station Electric Distribution Systems Voltages", December 22, 1980.
b.
NRC generic letter to all Power Reactor Licensees, " Staff Position Rela-tive to the Energency Power Systems for Operating Reactors", June 6,1977.
The FPC response to item 8 stated:
It is proposed to keep the existing undervoltage relays at their present setpoint of approxipately 555.
It is further proposed that a second set of undervoltage relays be added to the 4160V ES buses.
These relays would be solid state - in-stantaneous relays which would be set to trip at 90L' voltage.
A total time delay of 10 seconds would be used before the 901: voltage level would initiate transfer to the diesel generators.
The scnedule for ccm?leting the engineering package for effecting this cnange would be approximately April 1, 1981. The actual equipment chance could be per-formed during the refueling outage presently planned for Fall 1931, provided equipment. deliveries could be met.
The existing undervoltage scheme will still be used fcr initiating a cead cas transfer to the diesel generators.,
This proposal, in principle, is acceptable.
However, we need further details on your, design as previously requested in referenge b.
. o. >
1.
Verify that the selection of the voltagc and time setpoints were determined from your analysisa of voltage requirements of the class 1E loads at all distribution system voltage levels.
2.
Verify that the voltage nrotection includes coincidence logic to prevent spurious trips of offsite power.
e
- =
3.
Verify that the time delay on the second-level undervoltage relay logic a) does not exceed the maximum time delay that is assumed in the FSAR accident analysis (including diesel starting time),
b) minimizes the effect of short-duration disturbances reducing the availability of the offsite power sources.
l c) does not result in failure of safety systemstor components.
4.
Verify that the voltage monitors automatically initiate the disconnection of offsite power sources whsever the voltage setpoint and time-dels.r i
limits have been exceeded.
5.
Verify that the voltage monitor design satisfies the requirements of IEEE 4
std 279-1971.
6.
Supply preliminary proposed technical specifications in accordance with the-model technical specificationsb.
These should include limiting conditions -
of operation, trip setpoints, with upper and lower limits and allowable time delays.
7.
These same. technical specifications should include the tes_ ting requirements 4
to demonstrate the full operability and indecendence of the onsite power b
sources per position 3,
A