ML20153C676
| ML20153C676 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 08/19/1988 |
| From: | Langford D Office of Nuclear Reactor Regulation |
| To: | Bram S CONSOLIDATED EDISON CO. OF NEW YORK, INC. |
| References | |
| TAC-69025, NUDOCS 8809010242 | |
| Download: ML20153C676 (3) | |
Text
r August 19, 1988 9'
CORRECTED Af1ENDMENT Docket No. 50-247 DISTRIBUTION hart (4) local POR Wanda Jones Mr. Stephen B. Bram PDI-1 Rdg.
ACRS(10)
Vice President, Nuclear Power OGC GPA/PA Consolidated Edison Company SMcNeil ARM /LFMB of New York Inc.
DLangford EJordan Broadway and Bleakley Avenue MSlosson EButcher Buchanan, New York 10511 CYogan BGrimes SVarga DHagan
Dear Mr. Bram:
EBoger PSwetland e
SUBJECT:
EMERGENCY AMENDMENT TO INCREASE THE DESIGN SERVICE WATER TEMPERATURE LIMIT TO 90'F (TAC 69025) i The Comission has issued the enclosed Amendment No.135 to Facility Operating License No. OPR-26 for the Indian Foint Nuclear Generating Unit No. 2.
The amendment consists of changes te the Technical Specifications (TS), the TS Basis, and the Updated Final Safety Aitalysis Report (UFSAR),
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This amendment completes the Commission action initiated in our letters of Auoust 5, 1988, "Temporary Waiver of Compliance," and August 12, 1988, "Modified Walver of Compliance," in response to the Consolidated Edison application of August 4, 1988 as supplemented on August 5, 10, 16 and 18, 1988.
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i This amendment temporarily modifies 15 5.2.C. "Containment Systems," TS Basis i
page 3.3-10 and UFSAR Table 9.6-1, "Essential Service Water Requirements at 75'F i
River Water Temperature," by int:reasing the design inlet water temperature limit for the service water system from 85'F to 90'F.
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On October 1, 1988 at 12:01 a.m., this temporary amen h nt shall expire and i,
the design limit for maximum service water temperature shall revert to 85'F.
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A copy of the related Safety Evaluation is enclosed. A Notice of Issuance 1
and Final Determination of No Significant Hazards Consideration and Opportunity 1
for Hearing will be included in the Comission's next regular bi-weekly Federal Register notice.
Sincerely, L
j GrW531 W W
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k David Langford, Acting Project Manager Project Dlrectorate I-1 l
Division of Reactor Projects. I/II i
Enclosures:
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1.
Amendment No, to DPR-26
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2.
Safety Evaluation 1
CORRSCTED ANFNDMENT i
cc: w/ enclosures
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See next page
- SEE PREVIOUS CONCURRENCE gg
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PDI-1 PDI-1 OGC PDI-1 AD:DRP!/II i
SMcNeil DLangford RCapra BBoger 8/ /_88 _
8/4/88 8/ /88 S/t5/88 8/t.5/88 kO W *$L
August 19, 1988 I
Docket No. 50-247 DISTRIBUTION Docket File WKane NRCPDR TBarnhart(4) local PDR Wanda Jones Mr. Stephen B. Bram PDI-1 Rdg.
ACRS(10)
Vice President Nuclear Power OGC GPA/PA Consolidated Edison Company SMcNeil ARM /LFMB of New York, Inc.
DLangford EJordan Broadway and Bleakley Avenue MSt.osson EButcher Buchanan, New York 10511 CVogan BGrimes 1
SVarga DHagan l
Dear Mr. Bram:
BBoger PSwetland
SUBJECT:
EMERGENCY AMENDMENT TO INCREASE THE DESIGN SERVICE WATER TEMPERATURE LIMIT TO 90*F (TAC 69025) 1 The Comission has issued the enclosed Amendment No.135 to Facility Operating License No. DPR-26 for the Indian Point Nuclear Generating Unit do. 2.
The amendment consists of changes to the Technical Specifications (TS), the TS Basis, and the Updated Final Safety Analysis Report (UFSAR).
1 This amendment completes the Comission action initiated in our letters of August 5,1988, "Temporary Waiver of Compliance," and August 12, 1988, "Modified l
Waiver of Compliance," in response to the Consolidated Edison application of August 4, 1988 as supplemented on August 5, 10, 16 and 18, 1988.
i This amendrent temporarily modifies TS 5.2.C. "Containment Systems," TS Basis page 3.3-10 and UFSAR Table 9.6-1, "Essential Service Water Requirements at 75'F River Water Temperature," by increasing the design inlet water temperature limit for the service water system from 85'F to 90*F.
On October 1.1988 at 12:01 a.m., this temporary amendment shall expire and the design limit for maximum service water temperature shall revert to 85'F.
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Comission's next regular bi-weekly Federal Register notice.
Sincerely.
i as signed i
David t.angford, Acting Project Manager Project Directorate I-1 Division of Reactor Projects, I/I!
Enclosures:
1 1.
Anendment No.135 to DPR-26 i
2.
Safety Evaluation cc: w/ enclosures See next page g
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PDI-1 PDI-1 OG PDI-1 AD(- PI/II SPcNe[ @
Dlangford S
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RCapra BBo er Bf (f88 /'
8//f/88 8/ /88 8/g /88 8/ /88 il
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Mr. Stephen B. Bram Indian Point Nuclear Generating Consolidated Edison Company Station 1/2 of New York, Inc.
Cc:
Mayor Village of Buchanan Director Technical Development 236 Tate Avenue Programs Buchanan, New York 10511 State of New York Energy Office Agency Building 2 Ms. Donna Ross Empire State Plaza New York State Energy Office Albany, New York 12223 2 Empire State Plaza 16th Floor Mr. Peter Kokolakis, Director Albany, New York 12223 Nuclear Licensing Power Authority of the State of New York 123 Main Street Mr. Jude Del Percio White Plains, New York 10601 Manager of Regulatory Affairs Consolidated Edison Company of New York, Inc.
Mr. Walter Stein Broadway and Bieakley Avenue Secretary - NFSC Buchanan, New York 10511 Consolidated Edison Company of New York, In.
Senior Resident Inspector 4 Irving Place - 1822
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U.S. Nuclear Regulatory Comission New York, New York 10003 Post Office Box 38 Buchanan, New York 10511 Regional A hinistrator, Region I j
U.S. Nuclear Regulatory Cmenission Mr. Brent L. Brandenburg 475 Allendale P.oad Assistant General Counsel King of Prussia, PA 19406 Consolidated Edison Company of New York, Inc.
4 Irving Place - 1822 Charlie Donaldson, Esquire New York, New York 10003 Assistant Attorney General l
New York Department of Law 120 Broadway New York, New York 10271
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UNITED STATES NUCLEAR REGULATORY COMMISSION i
W ASHING TON, D. C. 20656 kg*....
CONSOLIDATED EDISION COMPANY OF NE*.1 YORK, INC.
DOCKET NO. 50-247 INDIAN POINT NUCLEAR GENERATING UNIT NC. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 135 License No. OPR-26 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Consolidated Edison Company of New York. Inc. (the licensee) dated August 4, 1988, as supplemented August 5, 10, 16 and 18, 1988, complies with the standards and requirements of the Atomic Energy
- t of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter It B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activ nies will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health sud safety of the p *lic; and a
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The issuance of this amendment 's in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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Accordingly, the license is am nded by changes to the Technical Specifications as indicated ia the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-26 is hereby amended to read as follows:
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. (2) Technical Specifications The Technical Specifications contained in Appendices t
A and B as revised through Amendment No.135, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is temporary and shall be used only once. Thia emendment is effective as of the date of its issuance and shall be implemented innediately. At 12:01 a.m. on October 1, 1988, this amendment shall expire and 1) the Amendment No.101 version of TS page 3.3-10 and 2) the Amendment No. 132 version of TS page 5.2-2 both shall be reinstated.
FOR THE NUCLPAR REGULATORY COMMIS$10N Bruce A. Boger, Assistant Director for Region I Reactors Division of Reactor Projects, I/I!
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Attachment:
l Changes to the Technical Specifications Date of Issuance: August 19, 1988 t
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Sa'a to UNITED $TATES
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NUCLEAR REGULATORY COMMISSION 5
WASHING TON. D. C. 20006 ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 135 TO FACILITY OPERATING LICENSE NO. OPR-26 i
DOCKET NO. 50-247 Revise Appendix A as follows:
Remove Pages Insert Pages 3.3-10 5.2-2 l
00 NOT REMOVE THE 10ENTICAL PAGES ISSUED BY AMENDMENT NOS. 101 AND i
132. RESPECTIVELY. They are to be reinstated upon expiration of the tecporary changes issued herewith.
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The requirement regartlag the aksiasm munber of 32 pusys the;t eAn be energised when acs tempereture is less than er equs1 to 319 F la dieeussed under 8
speelfication 3 1.A.
The sentainment eseling and lodine reeeni funettons are provided by two independent eyetens (a) faa eeelers plus shareest filters and th) eentainment spray with sodium hydreside a ddition.
During noemel power operatien, the five fan eeelers are required te remove heat leet free equipment and piping wit.hin sentairment at design eendittens (with a sceltag water toeperature of 90*F).I43 In the event of a Design Basis Aseident, l*
any one of the following eenhinations will provide suffielent eeeling to i
reduce eentainment pressure at a rate consistent with limiting eft-site deses to acceptable values (1) f1=e fan-eeeler units, (2) two sentainment spray pumps,.3) three f an-seeler units and one spray pump.
Aloe in the event of a I
Design assis
- Aseident, three sha rcoal filters (and their. asseelated l
recirculation f ans) in operation, alent with one sontainment sprey pump ' and oodium hydroulde addition, will reduce airborne organie and melocular iodine activities sufficiently to limit ef t-site deses to aseeptable values.
These eenstitute the minimum safeguards for ledine resenval, and are capahin 'ef belag operated on emergency power with one diesel generator inoperable.
If off eite power is availtble er all diesel generators are operating tb--
provide emergency power, the remaining installed lodine sameval equipment itwo eharcoal filters and their associated fans, and one sentainment spray pump and sodium hydroulde additten) can be operated to provide iodine removal la easess of the minimum requirements.
Adequate power for operation of the redundant eentairment heat removal systems (i.e.,
five fan-coeter units er two esatainment spray pumps) f.e assured by the availability of off-site power er 1
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operation of all emergesc'y diesel generators.
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one of the five fan oveler smits is permitted to be lamperable euring power
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operation. This is an ahmesmal operating situation, is that the normal plant l
operating procedures 1. squire that an inoperable faa eeeler he repaired as seen l
as practical.
l Bowever, heessee of the difficulty of aseese se make repaire, it is layertant l
sa eseasien to be able to operate temporarily witheet at least see fan-veeler.
Oseyeasattee for this mode of operaties, is provided by the high l
l degree of redundamey of esenat-t seeltag systema enring a Design assis t
l neeldent.
Tne component oneling System is different from the system dietussed aheve in
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that the ymye are se lesated la the Auxiliary Bailding as te he seeestible Amen h nt me. 181 135 3 3-10 i
A cooling u3ter teTer3ture of 90'F it in e'fect until 0001 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
j October 1, 10 E, at 5hich time the desien limit for the coolin, j
Nter terce ature will revert to 83 F.
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The automatic Phase A ecdtainosat is41sttee (trip) valves are actuated to the elesed peettien either naaually ev by an automat-teally derived safety tajeetles signal.
the assematie Phase 8 eentainment inelation valves are tripped eleeed by assematie or l
emanal containment spray actuaties.
The setusties system is l
4 designed seeA taat ne s tagie esegenent fattere will peevent contalmesat teetatica if rew & red.
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containeemt svetees l
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The contalmeent vestal inas sa laternal opvay eyeten which is capable of providtag a dietatheted herated we,ter spray of at least 2200 gpe.
ouriag the tattial posted of spray operetten, sodium hydroside woul the removal of todi'ne,4 he added to the spray water spresse i
from the eestainment atseephere, i
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The containment veneel has an internal roeirculatten systes which includes five faa eeeler unite (eentsifwgal fame and water eeeled 4
heat enchangers), with a total heat reseval espability et at least 304.5 'eTU/Wr. undet eenditions fellowing a f
laat accident and at service weter tassersture of 97F.ge A14 the l,
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fan cooler units are equipped with activates charcoal filters te remove volatile t041ne followine an accident.
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Referencee 1
(1) FSAA Section 3.1 (2) FSAA section 5.1.3.7 4
(3)
FSAR Sectica 4.3
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(4) PSAA Section 4.r.
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j Amendnent Me. 131 135 k
5.2-3 i
A cooling water temerature of 90*f is in effect until 0001 hears, October 1.1930, at which tire the desinn lilit for the c0 cling rater temperature will revert to 85 F.
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UNITf 0 s1 ATES
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g NUCLEAR REGULATORY COMMISSION 7,
s W ASHING TON, D. C, 20666 e....*
SAFETY EVALUATION BY TPE OFFICE OF NUCLEAR REACTOR REGULATION kELATED TO AMENDMENT NO. 135 TO FACILITY OPERATING LICENSE NO. OpR.26 CONSOLIDATED EDISON COMPANY OF NEW YORK, INC.
l INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 00CKET NO. 50-247 INTRODUCTION By letters dated August 4, 5, 10, 16 and 18, 1988 Consclidated Edison Company of New York, Inc. (Coned, the licensee) requested an emergency change to the plant Technical Specifications (TS) and Updated Final Safety Analysis Report (UFSAR)forIndianPoint. Unit 2.
The proposed amendment would modify TS 5.2.C.
"Containment Systems," the TS Sisis page 3.3-10 and UFSAR Table 9.6-1, "Essential 1
Service Water Requirements at 75'F River Water Temperature," by increasing the design inlet water temperature limit for the service water system (ultimate heat sink) frau 85'F to 90*F. The proposed change was prompted by the current drought and heat wave which have resulted in increased temperatures and reduced flow t
rates of the service water source, the Hudson River, thus causing the service 1
water temperature to exceed the specified limit of 85'F.
Thoughpeakandaverage 1
water temperatures in July and August 1988 have been 5'F to 10 F higher than expected, the licensee anticipates that peak water temperatures will be well below 85'F by October 1, 1988. Consequently, this change will remain in effect until 12:01 a.m. on October 1,1988 at which point the temperature limit shall revert to 85'F.
On August 5, 1988 and August 12, 1988, the NRC issued waivers of compliance from the 85*F cooling water temperature limit for temperatures up to 87'F and 90'F respectively. These waivers were required to prevent the unit from shutting down because of the then existing heat wave.
These waivers expired l
at 4:00 p.m. on August 19, 1988.
EVALUATION The service water system is designed to supply cooling water from the Hudson River to safety-related and nonsafety-related components necessary for nonnal plant operation and for post-accident safe shutdown conditions. UFSAR Section 9.6.1 describes the & sign basis of the service water system, and Table 9.6-1 Itsts the service uter rmirements for essential loads which includes both safety-related and nonsdety-related components cooled by the service water i
system. The licensee assessed the ir. pact of the proposed higher service water i
temperature limit on each component listed in Table 9.6.1, which includes the containment fan cooling unit coils, component cooling water coolers, diesel generators, turbine oil coolers, seal oil coolers / steam generator feed pump oil coolers, radiation sample coolers, air compressor heat exchanger, service water pump strainer blowdown, and central control room air conditioner.
In addition.
1 the imptet of the higher service water teeperature on the containment fan cooling unit motor coolers was also assessed.
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j 2-Containment Fan Cooling Units The higher service water inlet temperature to the containment fan coolers results in an increase in the service water flow requirements in order to maintain design basis containment heat removal capability.
In an earlier analysis, the licensee showed that the containment het.t removat requirements for the fan coolers were reduced from the value specified in the UFSAR due to revised mass and energy release data for the postulated design basis LOCA.
This revised analysis of containment heat removal requirements was reviewed and found acceptable by the staff in the Safety Evaluation Report transmitted to the licensee by letter dated June 29, 1988.
In the licensee's current saftty assessment, the previously approved heat removal analysis is used to demonstrate that the increase in service water flow requirements due to the increase in service water temperature is compensated for by the reduction in the heat removal requirement due to the change in mass and energy releases following a design basis LOCA.
The licensee s assessment showed that adequate containment heat removal capability is provided.
Component Cooling Water System Westinghouse perfomed an assessment for the licensee of the impact of the elevatedservicewatertemperatureonthecomponentcoolingwater(CCW) system perfomance following an accident and during nomal operation.
The analysis 1.
confirmed that adequate cooling of essential components served by the CCW system can be provided with the 90'F service water system temperature. However, it was determined that for a service water temperature of 90'F, operator actions are required to limit the CCW temperature 1) to less than 105'F, the continuous rating for the reactor coolant pump themal barriers, during normal operation, and 2) to less than 152'F during post-LOCA recirculation or alternate cooling sources would be needed to cool the safety injection pump seals. Consequently, the licensee has modified the associated nomal and emergency operating procedures to provide guidance to the operators to ensure adequate CCW flow during normal i
operation and accident conditions.
For normal operations, procedure requires l
the operator to restore CCW temperature to below 105'F within two hourt of l
j exceeding it by increasing the service water flow, which is normally throttled, 1
i to the CCW beat exchangers.
The emergency operating procedure requires the l
isolation of CCW flow to the spent fuel pool heat exchanger during the recirculatien i
l phase of the loss of coolant accident if less than two component cooling water pumps are operable. This approach is acceptable as qualified spent fuel pool makeup is available thus ensuring that the spent fuel pool water level will be maintained. With these procedural changes, the licensee has demonstrated the I
ability to provide adequate cooling to the CCW system during nomal and accident conditions with a service water temperature of 90'F.
j Emergency Diesel Generators Service water is provided to the emergency diesel generators (EDGs) to remove heat from its lube oil system, through the lube oil coolers, and subsequently, to cool the EDG's by removing combustion generated heat through the jacket water cooling system.
ALCO, the manufacturer of the EDGs, has evaluated coepanent I
1 perfomance data and detemined that 90'F service water, provided to cool the i
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EDGs, will not adversely affect the EDGs at full rated load as the EDG lube oil will continue to adequately cool the EDG's bearings and sufficient heat removal capability shall continue to be provided by the jacket water cooling system to ensure that the EDG does not malfunction or trip due to over-temperature conditions.
MITIGATING FACTORS To ensure that adequate heat removal capability is provided to the containment fan cooling units, the CCW system and the EDGs, the licensee has comitted to perfoming an orderly plant shutdown to hot shutdown, utilizing nomal plant operating procedures, if service water inlet temperature exceeds 90'F over a two hour period.
The plant shall be placed in hot shutdown within seven hours from the point in time whence the service water temperature initially exceeded 90'F.
l Furthemore, the licensee has comitted to monitoring service water temperature at least once per hour and CCW temperature at least once every two hours when f
the service water inlet temperature exceeds 85'F.
This monitoring will ensure I
i that, durir.g normal plant operations, adequate cooling is provided to the reactor coolant pump thermal barriers by CCW to prevent these themal barriers from being damaged by exceeding their continuous rating of 105'F or their two hour rating of 125'F.
STAFF CONCLUSION Based on the licensee's safety assessment for safety-related equipment cooling requirements at the higher service water system umperature, the staff concludes that the proposed emergency change to the Technicai Specifications to increase the service water inlet temperature to 90'F to be aceptable on a temporary basis until October 1, 1988. The licensee's continuing detailed analysis is considered i
confimatory and r.ay be used to support an eventual permanent Technical i
Specification change.
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FINAL NO SIGNIFICANT HAZARDS CONS 10ERATION DETERMINATION The Comission's regulation,10 CFR 50.92, states that the Comission may make a final detemination-that a license amendment involves no significant hazards consideration if operation of the facility in accordance with the amendment 4
would not:
- 1) involve a significant increase in the probability or consequences of an accident previously evaluated; or
- 2) create the possibility of a new or different kind of accident from i
any accident previously evaluated; or 3) involve a significant reduction in a margin of safety.
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The only previously evaluated accidents possibility affected by this amendment are the LOCA and the loss of offsite A.C. power event.
For a LOCA the 5'F increase to 90*F service water temperature could have the potential to affect
- 1) peak containment pressure by reducing the heat removal capability of the containment fan cooler units, 2) core reflood and fill by reducing CCW cooling to the safety injection pump seals, and 3) all safety equipment and functions powered by the EDGs due to the reduction in the heat removal capability of the EDG jacket water cooling system and lube oil cooler. The loads powered by the EDGs could be similarly affected for the loss of offsite A.C. power event.
The licensee has evaluated the possibility of these effects and has detemined l
that 1) peak containment pressure from a LOCA would not increase as the containment fan cooler units still retain the minimum heat removal capacity previously i
l detemined to be required. 2) with the previously specified revision to the E0Ps, I
adequate CCW flow will continue to be provided to the safety injection pump seals to assure their continued operation, and 3) adequate heat removal capability is still provided to adequately cool the fully loaded EDGs and EDG lube oil to ensure that they will not malfunction or trip due to over-temperature conditions.
Additionally, the licensee's comitment to shutdown if service water temperature exceeds 90*F for more than two hours assures that these functions will not be seriously degraded or reduced during peak river temperature periods. Consequently, the Wr staff has detemined that operation of the facility with a service water in.vt i.emperature of 90'F will not involve a significant increase in the probability or consequences of any accident previously evaluated, j
l Similarly, the NRC staff has detemined that this proposed amendment would not create the possibility of a new or different kind of accident from any previously evaluated as the systems affected by increasing service water temperature to 90*F still fmtion as designed and no other changes to the plant design or operation are being made other than raising the service water temperature from 85'F to 90'F.
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Finally, these proposed amendments do not involve a significant reduction in any margin of safety as peak containment pressure for a LOCA is unchanged and i
all safety and safety-related equipment affected still fully perfom their intended functions.
STATEMENT OF EMERGENCY CIRCUMSTANCES i
The service water system was designed to operate with a maximum temperature of 85'F.
This water is removed directly from the Hudson River.
Historically, the maximum river temperatures have occurred during July and August with an average peak temperature of 81'F.
However, this year as a result of the prolonged drought and extended heat wave, with 4tsspheric temperatures running between 90'F and 100'F the river water volume and flow rate have been reduced and the water I
temperatures have likewise increased.
Furthermore, as the river volume has decreased, the temperature of the service water discharge has had a greater effect 3
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upon the overall temperature of the river near the facility. Consequently, the average and peak river water temperatsres the facility has experienced in July and August 1988 have been approximately 5'F to 10'F above normal. This increase has been dependent upon tidal variations which can cause the heated service water discharge to flow towards and be taken up by the service water intakes.
Upon determining the size and severity of these temperature increases, the licensee promptly informed the NRC staff of this problem and bargan analyses to justify operation with a service water temperature of 90'F.
The staff has concluded that an unavoidable emergency situation does exist that would unnecessarily cause the shutdown or derating of the facility due to these higher service water temperatures and as such, warrants the emergency amendment procedures provided by 10 CFR Part 50.91.
STAFF CONSULTATIONS The appropriate representative of the State of New York was notified of this amendment. The State of New York cot: tact had no comments.
ENVIRONMENTAL CONSIDERATION This amendment changes a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part. 20. The staff has determined that the amendment involves no significarV incr' ele in the amounts, and no significant change in the types, of any effluents that may le released offsite, and that there is no significant increase in iilividal or sumulative occupational radiation exposure.
The Commission has We a f(nal no significant hazards consideration finding with i
respect to this amerh ent. Accordingly, the amendment meets the eligibility criteria for categorisal exclusion set forth in 10 CFR 551.22(c)(9).
Pursuant to 10 ',FR 651.72(b). no environmental impact statement or environmental assess-ment need be prepared in connection with the issuance of the amendment.
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CONCLUSION We have concluded. based on the considerations discussed above. that:
(1) this ernrgency situation could not be avoided; (2) the licensee acted in a timely manner with respect to responding to this emergency. (3) the amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated, does not create the possibility of a new or different type of accident from any evaluated previously, and does not involve a significant reduction in margin of safety. (4) there is reasonable assurance that the health
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4 6-and safety of the public will not be endangered by operation in the pi manner; and (5) such activities will be conducted in compliance with -
Connission's regulations and the issuance of this amendment will not t to the connon defense and security or to the health and safety of the PRINCIPAL CONTRIBUTORS:
i C. Y. Li S. McNeil Dated: August 19, 1988 I
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