ML18040B016

Misuse of Valve Resulting in Vibration & Damage to Valve Assembly & Pipe Supports

ML18040B016
Person / Time
Site:	Susquehanna
Issue date:	07/07/1983
From:	Ellen Brown NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
To:
Shared Package
ML17139B653	List: ML17139B652 ML18040B016
References
TASK-AE, TASK-E315 AEOD-E315, NUDOCS 8308040693
Download: ML18040B016 (31)

Text

AEOD ENGINEERING" EVALUATION REPORT*

UNIT::,Susquehanna.

1 DOCKET'O'.;

50-382"'ICENSEE:.

Pennsyl vania Power E, Light Company NSSS/AE;.

GE/Bechtel EE REPORT'O..: AEOD/E315 DATE..

July 7,, 1983 EVALUATOR'/CONTACTS':

Earl J.

Brown SUBJECT flISUSE OF VALVE'ESULTING IN VIBRATION AND DANGE; TO THE. VALYE.

ASSEYiBLY"AND PIPE'UPPORTS, EVENT DATES:

February 18,. 1983 (LER 83'-034) and, April 7;.. 1983 (LER 83.-056')'Ut 1MARY This, report, represents.

an evaluatioo: of two. licensee. event. reports (LERs) involving operation of. the: residuaT heat removal system (RHR) in the. shutdown cooling mode at the Susquehanna Unit 1 plant..

The first event identifies damage.to tbe LPCI system injection throttl'e valve, and.'ipe. supports-. that; was caused by severe vibration. of the.. system from throttTing the..val;ve outside. the. optimum flow rate range.,

The.

second. event identifies;

a. situation in wbi'ch a: test; to. determine. the: capability of the: RHR.heat exchanger.. led-to excessive. vessel and primary coolant'ooldown rates

.'nd;provides. insight. about; RHR'.system. operati'on; relative to the injection-thrott1e valve. vibra'tion in the first event;.

Based.'n

a. review of.. the'. information,, there:..is.- substantial'vidence that throttling the-valve,-outside the: optimum. range (misuse) resultedn excessive: vibration.and-subsequent. damage to the. val've. assembly and pipe supports..

However.;

ii= appears that

a. re'latively-low'evel'ecay: heat. cool'ing; requirement,,

in combination with some:- 1-imitations in-the.

RHR: system. design,. configuration and.fTow: control system,.

was. an important factor in tbe: decisi'on.to throttTe the; val:ve Approximately four.

months. after the; vibration event, the valve disc was found. separated from the stem

. with the cause suspected to be cracking of. wel'd Iocking tabs on. the disc. retaining nut. as a r'esult-of vibration Fajlure: of-this valve. before. or during LPCI sy'tem injection during a postuTated

.1'os's: of. coolant. accident'as potentially serious safety.consequences It appears. appropri'ate: to disseminate; informati'on-..about the. type. of damage that resul'ted. from. apparent. misuse.- of the valve In addition, current intermittent operation of the. RHR.sjstem in the'hutdown, cool'ing mode. appears to have: the potential for cumuTative:. damage: to. vaTve; operator motors.

Therefore, 'it. may

~ also. be. prudent: to review: the;. adeq'uacy of flow co'ntrol in the, shutdown cooling'ode "this document, supports ongoing AEOD and NRC activities and does not represent the. position or requirements-of'he responsible:

NRC program office.

DISCUSSION

~

~

This engineering evaluation reviews two.reports of events at Susquehanna Unit 1 (Docket 50-387).

The events are described in LERs83-034 and 83-056 and involve.

operation of the residual heat removal (RHR) system in the. shutdown cooling mode Although. the specific events are. independent, they are related in that one event (LER 83-056) illustrates system operational conditions'hat apparently influenced a decision to operate the low pressure coolant injection (LPCI) throttle valve outside the optimum throttling.range.

(LER 83-034).

The initial item. of interest was vibration and damage.to the LPCI.. system injection throttle valve. F0178.

To. understand the operational

aspects, Figure l. (from Ref. 1) il1ustrates the. "8" loop flow path from.the reactor recirculation loop through the RHR heat exchanger-and return to. the reactor:.recirculation loop.',"

Valve F0178 is just upstream of the recirculation. loop isolation check valve'0508, and, the normally closed injection valve,'0158.

The;RHg system design is sized for 10,000 gpm flow.through valve F0178.

The other valves invoTved. in RHR flow control or pathway. are the heat..exchanger bypass. valve, F0488, the heat exchanger inlet valve,

E0478, and heat exchanger outlet vaTve, F0038.

Valves F0178 and F0488 are globe valves and F0478 and F0038 are gate valves From; discussions with the. licensee staff, the RHR shutdown mode flow path. is.

established w,ith bypass valve F0488 full-open, flow control valve F0178 at a.

. position for 10,000

gpm, and either of the heat exchanger. inlet or outlet valve F0478 or F0038.,

closed such that'.alT flow bypasses the. heat. exchanger To establish heat exchanger flow, gate. va'ives F0478 and F0038 are positioned. in the full open position (either one. or both=would have to.be opened depending upon'hether one. or both had been closed)

."With.valves. F048B, F0478,.

and F0038 fuT1.'pen, the RHR flow is approximately 3/4-bypass,.flow and 1/4 heat. exchanger flow Therefore the minimum heat exchanger flow is,.about I/4 of full flow and can only be decreaseeey tbrot.tiing valve.F0178 lt appe..ars that this fTow distribution in combination with a very low level of decay heat created a.situation in which'it was desirable. to reduce flow.through the RHR heat exchanger but this could only be accomplished by throttling valve F0178.

LER 83-034, dated. March 18,.1983, provides information. about. an event at Susquehanna

..Unit'1 on February 18, 1983 The event involved severe vibration of the LPCI system injection valve F0178.

With the. RHR system in. the shutdown cooling mode, an operator making rounds discovered: that. the valve was vibrating severely..Further inspection reveal'ed that'he valve had lost its.packing, the position indicator had vibrated off, the adjacent saddle.-type pipe hanger.had.

two broken welds and weld cracks were observed on another pipe, hanger.

Irr addition, two.snubbers attached to the saddle-type. pipe hanger were replaced, although no observable damage.was.evident.

The 8

loop was declared inoperable.and.the A 1'oop was.placed in service.

Inspection of the A:1oop...while:.in service::revealed that several pipe hanger welds had cracks, but it was determined that operability was not.affected.

This. appears.to indicate the A loop had been operated in a manner similar to the 8 loop.

All damaged components were repaired.*

ecent reports e

and 3) indicate othee. damage-to the RHR F017B valve.

The resident inspector indicated.that recent investigations concerning RHR venting problems revealed that the valve disc had separated from the stem.

It was found that weld tabs which hold the disc nut locked. had cracked and permitted. the nut to back.off.

It is suspected that the previously reported vibration caused these weld tabs to crack.

The. vQration was.apparently caused by operation. of the. RHR shutdown cooling loop with flow rates. outside the optimum throttling range of F0178..

System operation outside the optimum throttle range of valve F017B was procedurally allowed by a.

temporary change notice which was implemented to provide a finer control of reactor coolant temperature..

7~peratin roce4qr.e was pqgie~~od~pvjsgd to ir,. ose o eratin restrictions that. wi prevent a recurrence of this event.

LER 83-056, dated ttay E, 1983, provides information about another event at Susquehanna Vnit l. on April 17, 1983.

This. event. involved operation of the RHR syste~ in the shutdown cooling mode.

The. original intent. was to conduct a startup test to determine the capability of the: RHR heat exchanger As a result of. an un-expected series of interactions, the test 1ed to excessive vessel and primary.

coolant cooldown rates

. An engineering analysis by the licensee-concluded, that the cooldown rates did. not impair'. structural integrity of the reactor coolant system.

This sequence of events involved. the same system.and components described for LER 83-034 and, shown in Figure. 1. It could involve either. the A loop (not. shown, but with the same configuration as the B loop with. valve numbers followed by A rather than B) or. the B; loop of RHR'rior to the test, reactor temperature/

pressure was.maintained with the shutdown cooling by usia the RHR heat exchan er for approximately five minutes out, of'.each hour.

As.peevious y escri ed, this m ans that valve. F was set or gpm ow, valve F048 was full open, and

'ither the heat exchanger inlet or discharge;:valve (F04T or,F003

.was closed. to

.. provide complete. bypass flow (no cooling from the heat exchanger

. 'he level of decay heat was. such. that. heat. exchanger

.Flow.was;.orrly needed for 5 minutes out of every hour ('ecall thaC thi's flow'as approximately. 3/4:.bypass and 1/4 heat. ex-changer).

Use of the heat exchanger.was." contro11ed by.alternate; opening and.'.

closing of valves. F047: and;F003 (i'=e,. if'FOIST was.closed, it;would'e opened':.to use: the; heat. exchanger;,

F003 therr would be closed. after five minutes to stop cooling;, after. 55'inutes,.F003'oul'd.

ba opened to start cool.ing;. F047 then would, be closed: to stop cooling)

The.test procedure to. determine. the. capability. of the shutdown heat exchanger apparently. specified. ful'1 10,000 gpm flow through the heat. exchanger (about four times the,',normal amount. that was'eeded for five minutes each hour).

Prior to the test,.'he heat excbanger had. been isolated for approximately one hour.

The.

test was started. by diverting all flow in RHR.loop A through the heat. exchanger by cl'osing bypass valve.F048.

This: heat exchanger bypass valve was fully closed approximately. three minutes after the-start'. of the.test.

When.a 60 F temperature drop in the suction line of the.. A recirculation loop was, approached, the startup, test.was aborted by opening the heat exchanger bypass. valve and isolating the heat exchanger.

By thah time;, the. temperature. drop was approximately 80o-90oF.and reactor 1evel was dropping due, to shrinka'ge.

The low level scram trip was subsequently actuated (this.was a-reactor protection system actuation only,. the reactor was not critical) and. shutdown cooling was isolated on an.RHR pump A trip.

This. sequence together. with subsequent.

action to'restore. reactor level resulted in excessive vessel and primary coo1ant cooldown rates.

Later in the sequence to return the RHR B loop to shutdown cooling,. the. heat exchanger discharge valve would not open due to an open motor winding, (burnout).

FINOINGS These two events illustrate. several issues concerning interaction aspects between system design and operation.

One'issue concerns valve assembly operation in a

t

~ manner for which it was notWtended.

Two.previous AEOD reports (Refs. 4.and 5) specifica1.1y address motor..burnout and valve vibration which were simiTar

- to those observed. in these. events at Susquehanna.

Reference 4 identifies several possible.

causes,.of

.motoe burnout

. One.'item was.motor: duty cycle which concerns the number of times a valve is operated within a. given time frame.

Based on the. manner in.

which the shutdown cooTing mode is, currently operated, the motor operator burnout cited. in LER 83-056, may be related. to.the frequent open and closing of the valve.

Similarly,.reference-5',...identifies several events in which vibration of the valve assembly apparentTy caused. by inappropriate. throttling, had resulted in loosening of the limit switches and.subsequent excessive closing torque-was applied.

Thus,,

the recent events, at-. Susquehanna appear to. be similar to previously observed phenomena.

Based on tbe preceding Ciscussion and related fol'lowup.activities for these.

licensee event-..reports,.

the following findings are provided; (I)

Valve misuse with throttling outside the. optimum range resulted in excessive.vibration and damage to the LPGA infection throttle. valve assembly and.the. system piping. supports.

Current procedures rely on administrative contraTs.to prevent.operation outside the optimum throttling range.

(2)

Vibration damage.was.

detected because.

an operator makigg rounds observed excessive. motion.

Previous'peration had appareatjy-already resulted in

~

weld, cracks in piping, supports, in. the A. loop but, these cracks.. were; not

detected, untiT. after the. va1ve. vibration in loop B. had-been observed.

(3')

The disc. separation'.from the stem'n the LPCE system injecti'on valve, F0178

. found. subsequent:.to the vibration, has potentially severe'.

'onsequences relative to L'PC?. operation

,.The separation could remain.

undetected.

because; position indicators..would. show fu11.open and inservice

'imp. tests would, normally not,have, flow through thi,s valve; Also, it.

would. be possible. for

a. degraded.disc-stem connection to fail under

~

conditions of: full LPCI: system injection. flow..

(4)

The combination of system design,. configuration, f1ow control system,,

and low level of decay heat'esulted,.in inteemittent.but frequent'ycling of the.

RHR. heat exchanger inlet. and outlet valves during the shutdown cooling mode. of operation.,

It. appears. that:.efforts to -provide either continuous or 1'onger periods. of'eat exchanger: fl'ow led to a conclusion that the only viable; short term acti'on, was; to..throttle the; LPCI system injection thr'ottle.

valve outside. the optimum range.

(5)

The current. operational'equence for the RHR system in the. shutdown cooling mode: with intermittent use (five minutes.. out. of every hour) of the. heat exchanger may have contributed to va.'Ive operator motor damage because of increased duty cycle..

However, higher levels of decay heat which would require more frequent valve cycling (something other than continuous. flow) could result in more rapid. motor operator fai-lure due to increased duty cycle requirements.

(6)

Shutdown cooling flow distribution has little if any control flexibility at the low end of heat exchanger flow.

A

'I (7)

The heat exchanger test procedure that led to the event reported in LER 83-056. appears to be inappropri ate in general because it could result in severe thermal'hock leads for the reactor vessel.

(8) It would: sem. appropriMe to develop an improved method of flow control'o permit continuous heat exchanger fl'ow during the shutdown cooling mode of RHR operation; This method should consider possib1e control of the service.- water flow as well as the. primary reactor water flow through the heat'xchanger.

(9)

The extent of valve assembly damage due to vibration indicates that such effects were not adequately accommodated. in design and qualification programs.

A similar finding was-cited in reference%.

t'ON CLUS IONS Based. on this. review and followup activities,. the damage to the LPCI injection throttl'e val've assembly and: support system appears to..be. among the most severe that has.been at5ributed to. vibration resul.ting from valve misuse.

If the damage had gone undetected,,

faiT'ure at a. later..time; could have adversely affected operation of. the. low pressure injection system 't is important to note that misuse of the: valve appears to-have been directly related to system flow limitations which in turn. resulted. from a combination of system design, configuration,. flow.

contro.T, system;. and, the low level of decay heat.

The. extent of valve. assembTy and pipe support damaae',

together with, the. interacti've aspects between design and operation appear to;.be; appropri,ate..material for an IE information notice.

In.

addition, curr ent..intermittent operation of-the. RHR,. system in.tbe shutdown cooling mode: appears to have the potential for-cumulative damage to valve'perator moto> s.

Therefore it. appears appropriate.to revi'ew the adequacy of.the. shutdown cooling mode system and flow controT. because such operation could have adverse effects on= equipment. that is. essentiaT'nder some accident conditions.

r REFERENCES 1..

HRC,. FSAR Susquehanna.-Steam, Electric. Station,. Figure 5.4 - 14b, "RHR Process Diagram."'.

BRC, PNO-I-83-60, Reactor Trip on Main Steam Line. High Radiation SignaT, Jun'i; 14,, 1983 3,

HRC, Morning. Report Region. I,. June 15,.1983, Susquehanna Unit 1.

4.

HRC,. E Z. Brown and: F. S. Ashe"Survey of V.alve. Operator-Related Events Occurring. During 1978, 1979. and 1980,," AEOD/C203',.dated Nay 1982'.

HRC; E..

J'.

Brown and':

S Ashe"InoperabTe Motor Operated Valve Assemblies Due. to Premature Degradation of Motors and/or Itapeoper Limit Switch/Torque Switch Adjus&ient," AEOD Engineering Evaluation Report E305, April 13,. 1983.

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Docket No, 50-387 NUCLEAR REGULATORY COMMISSIO WASHINGTON, D.C. 20555 August 16, 1983 I

I'RIBUTION:

o-~~t ntrol (5O-3 LBg2 Rdg.

EKylton RLPerch

FIngram, PA Docketing and Service Section Office of the Secretary of the Commission

SUBJECT:

SUSQUEHANNA UNIT 1 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT Two signed originals of the Federal Register Notice identified below are enclosed foryour transmittal to the Office ofthe Federal Register for publication. Additional conformed copies (

) of the Notice are enclosed for your use.

0 Notice of Receipt of Application for Construction Permit(s) and Operating License(s).

0 Notice of Receipt of Partial Application forConstruction Permit(s) and Facility License(s): Time for Submission of Views on Antitrust Matters.

0 Notice of Availabilityof Appiicant's Environmental Report, 0 Notice of Proposed Issuance of Amendment to Facility Operating License.

0 Notice of Receipt of Application for Facility License(s);

Notice of Availability of Applicant's Environmental Report; and Notice of Consideration of Issuance of Facility License(s) and Notice of Opportunity for Hearing.

0 Notice of Availabilityof NRC Draft/Final Environmental Statement.

0 Notice of Limited Work Authorization.

0 Notice of Availabilityof Safety Evaluation Report.

0 Notice of Issuance of Construction Permit(s).

0 Notice of Issuance of Facility Operating License(s) or Amendment(s).

XX Other:

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Enclosure:

As Stated Office of Nuclear Reactor Regulation oFFcE~

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Docket No.

5p 387 UNITED STATES NUCLEAR REGULATORYCOMMISSION WASHINGTON, D.C. 20555 August 16, 1983 RIB UTION:

v'eument Control (50-387)

No PDR LB42 Rdg.

EHylton RLPerch

FIngram, PA Docketing and Service Section Office of the Secretary of the Commission SuBJECT:

SUSQUEHANNA NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT Two signed originals ofthe Federal Register Notice identified below are enclosed foryour transmittal to the Office ofthe Federal Register forpublication. Additional conformed copies (

6 ) of the Notice are enclosed for your use.

Cl Notice of Receipt of Application for Construction Permit(s) and Operating License(s)

CI Notice of Receipt of Partial Application forConstruction Permit(s) and FacilityLicense(s): Time for Submission of Views on Antitrust Matters.

Cl Notice of Availabilityof Applicant's Environmental Report.

Q Notice of Proposed Issuance of Amendment to Facility Operating License.

C3 Notice of Receipt of Application for Facility License(s); Notice of Availability of Applicant's Environmental Report; and Notice of Consideration of Issuance of Facility License(s) and Notice of Opportunity for Hearing.

CI Notice of Availabilityof NRC Draft/Final Environmental Statement.

CI Notice of Limited Work Authorization.

0 Notice of Availabilityof Safety Evaluation Report.

CI Notice of Issuance of Construction Permit(s).

Cl Notice of Issuance of Facility Operating License(s) or Amendment(s).

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50-387 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 August 10, 1983

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LBA'2 Rdg.

EHylton RLPerch

FIngram, PA JV. Pre Docketing and Service Section Office of the Secretary of the Commission SuBJECT:

SUSqUEHANNA NOTICE OF CONSIDERATION OF ISSUANCE OF AHENSIIENT Two signed originals ofthe Federal Register Notice identified below are enclosed foryour transmittal to the Office ofthe Federal Register forpublication. Additional conformed copies ( 6

) of the Notice are enclosed for your use.

0 Notice of Receipt of Application for Construction Permit(s) and Operating License(s).

0 Notice of Receipt ofPartial Application forConsfruction Permit(s) and Facility License(s): Time for Submission of Views on Antitrust Matters.

0 Notice of Availabilityof Applicant's Environmental Report.

0 Notice of Proposed Issuance of Amendment to Facility Operating License.

0 Notice of Receipt of Application for Facility License(s); Notice of Availability of Applicant's Environmental Report; and Notice of Consideration of Issuance of Facility License(s) and Notice of Opportunity for Hearing.

0 Notice of Availabilityof NRC Draft/Final Environmental Statement.

0 Notice of Limited Work Authorization.

0 Notice of Availabilityof Safety Evaluation Report.

0 Notice of Issuance of Construction Permit(s).

0 Notice of Issuance of Facility Operating License(s) or Amendment(s).

XZ Other:

Enclosure:

As Stated Office of Nuclear Reactor Regulation

,OFFCE~

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Docket No.

50-387 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 August 8, 1983 F

Docketing and Service Section Office of the Secretary of the Commission DISTRIBUTION; Document Control (50-387)

LBA2 Rdg.

EHylton RLPerch

FIngram, PA jVo P5 rE-

SUBJECT:

NOTICE OF CONSIDERATION OF ISSUANCE OF ANENDNENT I

Two signed originals of the Federal Register Notice identified below are enclosed foryour transmittal to the Office ofthe Federal Register for publication. Additional conformed copies (6

) of the Notice are enclosed for your use.

Q Notice of Receipt of Application for Construction Permit(s) and Operating License(s).

Q Notice of Receipt of Partial Application forConstruction Permit(s) and Facility License(s): Time for Submission of Views on Antitrust'atters.

Q Notice of Availabilityof Applicant's Environmental Report.

Q Notice of Proposed Issuance of Amendment to Facility Operating License.

Q Notice of Receipt of Application for Facility License(s);

Notice of Availability of Applicant's Environmental Report; and Notice of Consideration of Issuance of Facility License(s) and Notice of Opportunity for Hearing.

Q Notice of Availabilityof NRC Draft/Final Environmental Statement.

Q Notice of Limited Work Authorization.

Q Notice of Availabilityof Safety Evaluation Report.

Q Notice of Issuance of Construction Permit(s).

Q Notice of Issuance of Facility Operating License(s) or Amendment(s).

NZI Other:

Enclosure:

As Stated Office of Nuclear Reactor Regulation DL:LBfI2 LA

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Docket No. 50-387 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 Duly 25, 1983 VK.

C ntrol NREXRIIR LB¹2 File EHylton

RPerch, FIngram, PA Docketing and Service Section Office of the Secretary of the Commission

SUBJECT:

Susquehanna Steam Electric Station, Unit 1 JPennsyvvania Power and Light Company )

Two signed originals of the Federal Register Notice identified below are enclosed foryour transmittal to the Office ofthe Federal Register for publication. Additional conformed copies ( 6

) of the Notice are enclosed for your use.

0 Notice of Receipt of Application for Construction Permit(s) and Operating License(s).

0 Notice of Receipt of Partial Application forConstruction Permit(s) and Facility License(s): Time for Submission of Views on Antitrust Matters.

0 Notice of Availabilityof Applicant's Environmental Report 0 Notice of Proposed Issuance of Amendment to Facility Operating License.

Notice of Receipt of Application for Facility License(s); Notice of Availability of Applicant's Environmental Report; and Notice of Consideration of Issuance of Facility License(s) and Notice of Opportunity for Hearing.

0 Notice of Availabilityof NRC Draft/Final Environmental Statement.

0 Notice of Limited Work Authorization.

0 Notice of Availabilityof Safety Evaluation Report.

0 Notice of Issuance of Construction Permit(s).

0 Notice of Issuance of Facility Operating License(s) or Amendment(s).

Rl Other:

determination and opportunity for hearing.

(application dated

Enclosure:

.As Stated Office of Nuclear Reactor Regulation DL:LB¹ /LA EH) 't 7/25 3

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UNITED STATES NUCLEAR REGULATORYCOMMISSION WASHINGTON, D.C. 20555 July 25, 1983

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nt Con Fil e EHylton Rperch

FIngram, PA Docketing and Service Section Office of the Secretary of the Commission

SUBJECT:

Susquehanna Steam Electric Station, Unit 1 (Pennsylyania Power and Light Company)

Two signed originals of the Federal Register Notice identified below are enclosed foryour transmittal to the Office of the Federal Register for publication. Additional conformed copies (

6

) of the Notice are enclosed for your use.

C3 Notice of Receipt of Application for Construction Permit(s) and Operating License(s)

Q Notice of Receipt of Partial Application forConstruction Permit(s) and Facility License(s): Time for Submission of Views on Antitrust Matters.

Cl Notice of Availabilityof Applicant's Environmental Report, 0 Notice of Proposed Issuance of Amendment to Facility Operating License.

Q Notice of Receipt of Application for Facility License(s); Notice of Availability of Applicant's Environmental Report; and Notice of Consideration of Issuance of Facility License(s) and Notice of Opportunity for Hearing.

CI Notice of Availabilityof NRC Draft/Final Environmental Statement.

C3 Notice of Limited Work Authorization.

C3 Notice of Availabilityof Safety Evaluation Report.

C3 Notice of Issuance of Construction Permit(s).

C} Notice of Issuance of Facility Operating License(s) or Amendmpnt(s).

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operating license and proposed no significant hazards consideaation determination and opportunity for hearing.

(application for amendment

Enclosure:

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Docket No, 50-387 UNITED STATES NUCLEAR REGULATORYCOMMISSION WASHINGTON, D.C. 20555 Apr)1 15, 1983 "IS c et F1 e (50-387 L '82 1

e EHylton RPerch

FIngram, PA Docketing and Service Section Office of the Secretary of the Commission

SUBJECT:

NOTICE OF ISBUANCE OF ANENDI'IENT NO. 14 TO LICENSE NO. NPF-14 FOR SUS(UEHANNA STEAN ELECTRIC STATION, UNIT 1 Two signed originals of the Federal Register Notice identified below are enclosed foryour transmittal to the Office ofthe Federal Register forpublication. Additionalconformed copies (

6

) of the Notice are enclosed for your use.

0 Notice of Receipt of Application for Construction'ermit(s) and Operating License(s),

/

0 Notice of Receipt of Partial Application forConstruction Permit(s) and Facility License(s): Time for Submission of Views on Antitrust Matters.

Q Notice of Availabilityof Applicant's Environmental Report.

0 Notice of Proposed Issuance of Amendment to Facility Operating License.

0 Notice of Receipt of Application for Facility License(s); Notice of Availability of Applicant's Environmental Report; and Notice of Consideration of Issuance of Facility License(s) and Notice of Opportunity for Hearing.

0 Notice of Availabilityof NRC Draft/Final Environmental Statement.

0 Notice of Limited Work Authorization.

0 Notice of Availabilityof Safety Evaluation Report.

0 Notice of Issuance of Construction Permit(s).

g Notice of Issuance of Facility Operating License(s) or Amendment(s).ND.'4 0 Other:

Enclosure:

AsSt ed Office of Nuclear Reactor Regulation OFFICE~

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+$4,'a Docket No. 50-387 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 March 9, 1983 TION:

Docket Fi LBk'2 File EHyl ton

FIngram, PA RPerch Docketing and Service Section Office of the Secretary of the Commission

SUBJECT:

NOTICE OF ISSUANCE OF AMENDMENT NO. 12 TO SUS(UEHANNA STEAM ELECTRIC STATION, UNIT 1 - LICENSE NO. NPF-14 Two signed originals of the Federal Register Notice identified below are enclosed foryour transmittal

'o the Office ofthe Federal Register forpublication. Additional conformed copies (

6 ) of the Notice are enclosed for your use.

0 Notice of Receipt of Application for Construction Permit(s) and Operating License(s).

0 Notice of Receipt of Partial Application forConstruction Permit(s) and Facility License(s): Time for Submission of Views on Antitrust Matters.

C3 Notice of Availabilityof Applicant's Environmental Report.

0 Notice of Proposed Issuance of Amendment to Facility Operating License.

C3 Notice of Receipt of Application for Facility License(s);

Notice of Availability of Applicant"s Environmental Report; and Notice of Consideration of Issuance of Facility License(s) and Notice of Opportunity for Hearing.

0 Notice of Availabilityof NRC Draft/Final Environmental Statement.

0 Notice of Limited Work Authorization.

C3 Notice of Availabilityof Safety Evaluation Report.

0 Notice of Issuance of Construction Permit(s).

xRI Notice of Issuance of Facility Operating License(s) or Amendment(s).

No.

12 0 Other:

Enclosure:

As Stated Office of Nuclear'eactor Regulation DL:LBI2I2 A

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DATE~

RRQ FORM 102 779

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Docket No.

"ISTRIBUTION..

UNITED STATES LBI'/2 File NUCLEAR REGULATORY COMMISSION EHyl Po n WASHINGTON, D.G. 20555

FIngram, PA February 24,'983 RLPerch Docketing and Service Section Office of the Secretary of the Commission SUBJECT. NOTICE 0$ ISSUANCE OF AMENDfIENT NO.

11 TO FACILITY OPERATING LICENSE NO. NPF-14, SUS(UEHANNA STEAN ELECTRIC STATION, UNIT 1 Two signed originals of the Federal Register Notice identified below are enclosed foryour transmittal to the Office ofthe Federal Register forpublication. Additional conformed copies ( 6

) of the Notice are enclosed for your use.

0 Notice of Receipt of Application for Construction Permit(s) and Op'crating License(s) 0 Notice of Receipt of Partial Application forConstruction Permit(s) and Facility License(s): Time for Submission of Views on Antitrust Matters.

0 Notice of Availabilityof Applicant's Environmental Report.

0 Notice of Proposed Issuance of Amendment to Facility Operating License.

0 Notice of Receipt of Application for Facility License(s);-Notice of Availability of Applicant's Environmental Report; and Notice of Consideration of Issuance of Facility License(s) and Notice of Opportunity for Hearing.

0 Notice of Availabilityof NRC Draft/Final Environmental Statement.

0 Notice of Limited Work Authorization.

0 Notice of Availabilityof Safety Evaluation Report, C

0 Notice of Issuance of Construction Permit(s).

g Notice of Issuance of Facility Operating License(s) or Amendment(s).ND.

11 0 Other:

Enclosure:

As Stated DL:LB82/ A OFFICE~

E SURNAME~......,.,.,

2/24/83 DATE~

NRC FORM I02 7

79 Office of Nuclear Reactor Regulation

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. Docket No.

5O 387 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 February. 14, 1983

. I'RIB UTION:

Document Control (50-387)

LBP2 Reading EHylton RLPerch

FIngram, PA

(

I Docketing and Service Section Office of the Secretary of the Commission NOTICE OF ISSUANCE OF NIENDHENT TO FACILITY OPERATING LICENSE-SUSqUEHANNA UNIT 1, ANENDWENT 'NO. lo Two signed originals of the Federal Register Notice identified below are enclosed foryour transmittal to the Office ofthe Federal Register forpublication. Additional conformed copies ( 6

) of the Notice are enclosed for your use.

0 Notice of Receipt of Application for Construction Permit(s) and Operating License(s).

C 0 Notice of Receipt of Partial Application forConstruction Permit(s) and Facility License(s); Time for Submission of Views on Antitrust Matters.

0 Notice of Availabilityof Applicant's Environmental Report.

. 0 Notice of Proposed Issuance of Amendment to Facility Operating License.

0 Notice of Receipt of Application for Facility License(s);

Notice of Availability of Applicant's Environmental Report; and Notice of Consideration of Issuance of Facility License(s) and Notice of Opportunity for Hearing.

0 Notice of Availabilityof NRC Draft/Final Environmental Statement.

0 Notice of Limited Work Authorization.

0 Notice of Availabilityof Safety Evaluation Report 0 Notice of Issuance of Construction Permit(s),

)I Notice of Issuance of Facility Operating License(s) or Amendment(s).

0 Other:

Enclosure:

As Stated Office of Nuclear Reactor Regulation OFFCE SURNAME~ KHyj..ta.n...w..

oATE~

2( 1 4/83 NRC FORM 102 7

79

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Docket No. 50-387 UNITED STATES NUCLEAR REGULATORy COMMISSION WASHINGTON, D.C. 20555 February 7, 1983 ISTRIBUTION:

Document Control (50-387)

LB82 Reading EHylton RLPerch

FIngram, PA Docketing and Service Section Office of the Secretary of the Commission

SUBJECT:

NOTICE OF ISSUANCE OF AIIENDNENT NO. 9 TO FACILITY OPERATING LICENSE-SUSgUEHANNA UNIT l Two signed originals of the Federal Register Notice identified below are enclosed foryour transmittal to the Office of the Federal Register for publication. Additionalconformed copies (6

) of the Notice are enclosed for your use.

0 Notice of Receipt of Application for,Construction Permit(s) and Operating License(s).

0 Notice of Receipt of Partial Application forConstruction Permit(s) and Facility License(s): Time for Submission of Views on Antitrust Matters.

E 0 Notice of Availabilityof Applicant's Environmental Report 0 Notice of Proposed Issuance of Amendment to Facility Operating License.

0 Notice of Receipt of Application for Facility License(s);

Notice of Availability of Applicant's Environmental Report; and Notice of Consideration of Issuance of Facility License(s) and Notice of Opportunity for Hearing.

0 Notice of Availabilityof NRC Draft/Final Environmental Statement.

0 Notice of Limited Work Authorization.

0 Notice of Availabilityof Safety Evaluation Report.

0 Notice of Issuance of Construction Permit(s).

>Q Notice of Issuance of Facility Operating License(s) or Amendment(s).

0 Other:

Enclosure; As Stated Office of Nuclear Reactor Regulation DL:,LB',LA, E,

0 2Z /83 OFFICE~

SURNAME~

OATE~

NRC FORM I02 779

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Docket No.

50-387 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 February 7> 1983 DISTRIBUTION:

c~

LBII2 Fil e EHylton RPerch

FIngram, PA Docketing and Service Section Office of the Secretary of the Commission

SUBJECT:

NOTICE OF ISSUANCE OF AhiENDIIENT NO. 8 TO FACILITY OPERATING LICENSE NO. NPF-14, SUS(UgHAhINA STEAN ELECTRKC, STATION Two signed originals ofthe Federal Register Notice identified below are enclosed foryour transmittal to the Office ofthe Federal Register forpublication. Additional conformed copies (

6 ) of the Notice are enclosed for your use.

Q Notice of Receipt of Application for Construction Permit(s) and Operating License(s).

Q Notice of Receipt of Partial Application forConstruction Permit(s) and Facility License(s): Time for Submission of Views on Arltitrust Matters.

C3 Notice of Availabilityof Applicant's Environmental Report.

Cl Notice of Proposed Issuance of Amendment to Facility Operating License.

C3 Notice of Receipt of Application for Facility License(s); Notice of Availability of Applicant's Environmental Report; and Notice of Consideration of Issuance of Facility License(s) and Notice of Opportunity for Hearing.

C3 Notice of Availabilityof NRC Draft/Final Environmental Statement.

i C3 Notice of Limited Work Authorization.

C3 Notice of Availabilityof Safety Evaluation Report.

Q'otice of Issuance of Construction Permit(s).

Ixl Notice of Issuance of Facility Operating License(s) or Amendment(s). Np.

8 Q Other:

Enclosure:

~As Stated Office of Nuclear Reactor Regulation OFFCE~

SURNAME~

OATE~

NRC FORM 102 7

7F DL:LBI'f LA EH, ~pt 2/7/83

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