ML20012B402
| ML20012B402 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 02/20/1990 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20012B398 | List: |
| References | |
| NUDOCS 9003140344 | |
| Download: ML20012B402 (3) | |
Text
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- pa atgk' UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20666 j
n SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGlt ATION
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REL ATED TO AMENDKENT NO. 27 TO FACILITY OPERATING LICENSE NPF-68 f
AND AMENDMENT NO. 8 TO FACILITY OPERATING LICENSE NPF-81 L
t GEORGI A POWER COWANY, ET AL.
DOCKETS NOS. 50-424 AND 50-425 l
V0GTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2
1.0 INTRODUCTION
l By letter dated November 7,1908, and supplanented Decent >er 1,1986, and i
Georgia Power Conpany,)6t 61., (the licensee) requested a change May 19, 1989, to the Technical Specifications (TSs Units 1 and 2.
The proposed anundnents would revise TS 3.3.3.6, " Accident r
Monitoring Instrumentation," to make the action requirements for inoperable containant hydrogen concentration monitors consistent with the requirements of TS 3.6.4.1, " Hydrogen Monitors."
1 2.0 EVALUATION
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The licensee has provided the following information in support of their request:
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The Yogtle T!is include Da contahwn; haroten monitors ir; the Containnunt Systems specification (3/4.6.4.1), consister.t with Generic Letter 83-37, "NUREG 0737
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Technical Specificaticus," and-the Westinghouse Standard Technical Specifications.
Yh sam monitors are also included in tha Accioent Monitoring Instry:sentetion specification (3/4.3.3.6).
Inclusion of the bydogen unitors in the Accf dent Monituring Instrunentation specification was based on the EC staff position that F49ulatory Guide 1.97, Category 1 instame.ntation should be subject to TS requ iremnts.
The fuct that the hyorogui monitors were aadressed by another TS may have been overlooked.
The Accident Monitoring Instrunentation specification places overly restrictive action requirements on the hydrogen monitors. With one of two monitors inoperable, 7 days are allowed to restore the inoperable monitor to operable status; with both nonitors inopertble, 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> are allowed to restore one n.oni tor.
This is inconsistent with the staff position in Generic Letter 83-37 and is inappropriate given the function these monitors perform. The hydrogen monitors provide indication and recording of post-loss of coolant accident (LOCA) containment hydrogen concentration.
They perform no control or trip functions and are not neeoed for immediate post-accident mitigative action.
Buildup of hydrogen in containant following a LOCA is a slow process. As discussed in final Safety Analysis F= port (FSAR) Section 6.2.5.3, with no recombiner operation,
-it takes 12 days for a cont >ustible mixture (4 volume percent hydrogen) to occur. With a single recombiner started on the second day or when the bulk containment 'conct.ntration reached 3.5 volune percent, the hydrogen concentration 9003140344 900220 PDR ADOCK 05000424 P
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2-is quickly reduced.
If the subject monitors were not available following a LOCA other means of The Post-Accident Sample System (PASS) hydrogen monitoring could be used.is capable of saspling 1
hydrogen concentration within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> after a decision is made to take a i
sample.
Grab samples can be obtaired from the PASS for laboratory analysis as
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a backup to in-line analysis.
J The NRC staff has reviewed the information provided by the licensee and finds l
that the proposed change is in accordance with Generic Letter 83-37.
Therefore, i
the proposed change is acceptable, t
3.0 ENVIRONMENTAL CONSIDERATg These amenenents involve changes to a requirement with respect to the use of a facility commnent located within the restricted area as defined in 10 CFR Part
- 20. The sta"f has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released off site, and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a proposed finding that the anendnents involve no significant lazards consideration, ano there has been no public couannt on such finding.
Accordingly, the ameneents meet the eligibility critaria for categorical exclusion set forth in 10 CFR 51.22(c)(?).
Pursuant to 10 CFR 51.22(b), no envirMmental impact statenant or anyironnental assessment nted be prepared in conrectivm w1Th the issuance of the arendments.
4.0,CJCELUSION The Commission made a proposed determination that the anendcents involve no I
significant hazards consideration which was published in the Federal Register on July 26,1989 (54 FR 31107), anti consulted with the State oTle'WgTa.
No puolic cor.ments were received, and the State of Georgia did not have any cornents.
The staff has concluoed, based on the considerations discussed above that: (1) endangered by operation in the proposed manner, and (2)y of the pub 1}
there is reasonable assurance that the health and safet such activitiss will be conducted in compliance with the Commission's regulations, ano the issuance of the anendments will not be inimical to the coninon defense and security or to the health and safety of the ptblic.
Principal Contributor: Jon B. Hop kins, PDII-3/DRP-I/II Dated: February 20, 1990 l
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- n DATED: February 20, 1990 AMENDMENT NO. 27 TO FACILITY OPERATING LICENSE NPF Vogtle Electric Generating Plant, Unit 1 AMENDMENT NO. 8 TO FACILITY OPERATING LICENSE NPF Vogtle Electric Generating Plant, Unit 2 DISTR' BUTION:
%MN NRC PDR Local FDR PDII-3 R/F Yogtle R/F SVarga 14-E-4 GLainas 14-H-3 DMatthews 14-H-25 RIngram 14-H-25 JHopkins 14-H-25 OGC-WF 15-B-18 EJordan MNBB-3302 GHill (8)
P1-137 ACRS(10)
P-135 GPA/PA 17-F-2 ARM /LFMB AR-2015 DHagan HNBB-3302 a
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