ML20215G072
| ML20215G072 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 10/10/1986 |
| From: | Koester G KANSAS GAS & ELECTRIC CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| KMLNRC-86-188, TAC-63108, NUDOCS 8610160472 | |
| Download: ML20215G072 (3) | |
Text
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KANSAS GAS AND ELECTRIC COMPANY
~*
THE ELECTA *C COMPANY
@LENN L NOESTER vect poterosm? muctsan October 10, 1986 fir. H. R. Denton, Director Office of FMclear Reactor Regulation U. S. Nuclear Regulatory Comission Washington, D. C.
20555 KMLNRC 86-188 Re:
Docket No. SPN 50-482 Subj: Residual Heat Removal System Operability with One Emergency Diesel Generator Removed from Service
Dear Mr. Denton:
The purpose of this letter is to provide information requested by your Staff concerning Residual Heat Removal (RHR) system operability with one emergency diesel generator removed from service.
During refueling outages at Wolf Creek Generating Station, one emergency diesel generator may be out of service coincident with a technical specification requirement for tw operable RHR trains.
This condition will exist for approximately five days during the first refueling outage.
Kansas Gas and Electric Company (KG&E) has concluded that both RHR trains can be considered operable in Modes 5 and 6 with one emergency diesel generator inoperable, provided non-emergency power is available to the RHR train affected by the inoperable diesel generator and that the unaffected RHR train has an emergency power supply and is otherwise operable.
KG&E believes that this is in accordance with thclear Regulatory Comission guidance provided by a Generic Intter dated April 10, 1980 and a letter from D. G. Eisenhut to C. E. Nore11us dated April 10,1983.
KG&E has augmented existing procedures to address a Staff inquiry regarding continued decay heat removal in Modes 5 and 6, concurrent with loss of all offsite power and failure of the operable emergency diesel generator.
Procedures GEN 00-007 and STS CR-002 have been modified to ensure, in Modes 5 and 6 when technical specifications require two operable RHR trains, the following:
- 1. Both RHR trains are operable, with one in operation, and capable of being powered from an operable emergency power cource, or; 00l 8610160472 861010 PDR ADOCK 05000482 P
'Is 201 N. Market - Wochtta, Kansas - Mad Address: PO. Box 208 I #chsta, Kansas 67201 - Telephone: Area Code (316) 2616451
iH.-R.Denton' October 10, 1986 KMDSC 86-188 Page 2
- 2. Two independent offsite circuits are available and aligned to' independent onsite Class lE distribution systens and one emergency diesel generator is operable in accordance with Technical Specification 3.8.1.2.b., and; I
- 3. Provisions have been inplemented to prevent unfiltered j
release pathways from containment to the environment within thirty minutes of loss of both RHR trains.
2 h existing off-normal procedure, OFN 00-015, Ioss of Shutdown Cooling (RHR), has been revised to specifically address core cooling with loss of all A.C.
power. This procedure specifically identifies and directs the utilization of three independent sources of makeup
- water to the Reactor Coolant System (RCS), ensuring continued decay heat removal in Modes 5 and 6 concurrent with a loss of all A.C.
i power.
N identified sources of makeup water and methods of RCS l-inventory addition would be utilized as necessary to ensure adequate' 1
RCS inventory is maintained for continued decay heat removal. 'In the
+
s 1
inprobable ' event of a loss of all A.C.
power during Modes 5 and 6 1
borated makeup water could first be supplied from the Safety Injection Accumulators.
Flow from the Accunulators would be controlled to ensure adequate BCS inventory. Secondly, borated makeup p
water could be supplied by gravity feed from the Refueling Water F
Storage Tank (RHST) into the RCS via the RHR system. RNST inventory T
could be replenished, if necessary, from the Fire Protection system when directed by the Shift Supervisor. Aligning Fire' Protection
,j' system discharge into the RCS via the RHR system is a third source of i
makeup water' and method of inventory addition delineated in this
}
off-normal procedure.
h aforementioned procedures have been written in accordance with
?
i existing plant procedures for procedure development. These procedures j
will~ be. reviewed and approved by the Plant Safety Review Connittee.
Operator training on the approved procedures will be conpleted prior to the plant being in Mode 5 or 6, with a technical specification requirement for two operable RHR trains and one emergency diesel generator removed from service.
1 h first refueling outage at Wblf Creek Generating Station is currently scheduled to begin on October 16,'1986.
KGEE firmly believes that the information provided in this letter fully addresses the plant condition of one emergency diesel generator removed from service concurrent with a technical specification requirement for two operable RHR systems as well as reflecting KG&E's continuing commitment to the safe and successful operation of Wb1f Creek i
Generating Station.
I l
1
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J. R. Denton October 10, 1986 KMLNBC 86-188 Page 3
~If you have any questions concerning this matter, please contact me or Mr. O. L. Maynard of my staff.
Yours very truly, A xt( d Glenn L. Koester Vice-President NLiclear GIK:hkc cc: RDMartin PO'Connor(2)
DIJohnson JCunnins i
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