ML20141D302

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Forwards Correspondence & Documents Re Emergency Planning Among Applicant,Nrc,Commonwealth of PA & Other Responsible Governmental Agencies,In Accordance W/Board 820601 Order. Related Correspondence
ML20141D302
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 03/27/1986
From: Cullen E
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To: Zitzer P
LIMERICK ECOLOGY ACTION, INC.
References
CON-#286-619 OL, NUDOCS 8604070481
Download: ML20141D302 (22)
v • d • e


Text

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-- DIED CUH4e sawn PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET 00LNtico P.O. BOX 8699 u NC PHILADELPHIA. PA.19101

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...................... uGCME Tigl 'y"-

DON ALD ELANNEN hkdN@

RUDOLPH A. CHILLEMI C. C. MIR M M A LL T. H. M AMER CO RN ELL FAUL AUERS ACH

.............. 6. ... fbrch 27, 1986 CDW ARO J. CULLEM, JR.

THOM AS H. MILLER, JR.

IREME A. MsMEN M A Ms. Phyllis Zitzer Limerick Ecology Action 762 Queen Street Pottstown, PA 19464 Re: Limerick Generating Station, Units 1 and 2 Docket Nos. 50-352 and 50-353 O (. ,

Dear Ms. Zitzer:

In accordance with the Board's Order of June 1,1982, I am forwarding to you copies of correspondence and doctanents regarding emergency planning among Applicant, NRC Staff, the Commonwealth of Pennsylvania and other responsible governmental agencies.

Very truly yours,

g d 4 ..

Edward J. Ct111en, Jr.

EJC,JR./pke Enclosures cc: See Attached Service List 0006q P

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- ... . _________-__-_-_-_____n. _ _ - _-

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cc: Troy B. Conner, Jr., Esq. (w/enclosup Ann P. Hodgdon, Esq. (w/enclosur jf Mr. Frank R. Romano (w/oenclosurei{P Phyllis Zitzer (w/ enclosure)

Mr. Robert L. Anthony (w/o d861oweh P2:33 Barry M. Hartman, Esq. (w/ enclosure)

Mr. Thomas Gerusky (w/o Ipsure)

Director, PINA (w/o p yge) .

Charles W. Elliott, Esq. (w/o encLoggh))U ""

Angus Love, Esq. (w/o enclosure David Wersan, Esq. (w/o enclosure)

Robert J. Sugarman, Esq. (w/o enclosure)

Kathryn S. Lewis, Esq. (w/o enclosure)

Spence W. Perry, Esq. (w/o enclosure)

Jay M. Gutierrez, Esq. (w/o enclost.re)

Atomic Safety 4 Licensing (w/o enclosure)

Appeal Board Atomic Safety 4 Licensing (w/o enclosure)

. Board Panel Docket 4 Service Section (w/o enclosure)

E. M. Kelly (w/o enclosure)

Timothy R. S. Campbell (w/o enclosure)

. nt.LAito cosaunnte

f. .

PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET . SNRC

! P.O. DOX 8699 PHILADELPHI A. PA.19101 $R 3l pp ;37

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Mr. Walter R. Butler, Director Docket No. 50-352 BWR Project Directorate #4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555 MAR 2 5198f

SUBJECT:

Limerick Generating Station Unit i Preservice Inspection

REFERENCE:

Letter, J. S. Kemper to W. R. Butler, dated October 22, 1985 FILE: COVT l-1 (NRC)

Dear Mr. Butler:

As we committed in the reference letter, we are pleased to provide the following information in response to NUREG-0991, Confirmatory issue

#12 (Sections 5.2.4.3 and 6.6.3).

The Commercial Service Date for the Limerick Generating Station Unit I has been established as February 1, 1986 and is reported herein, pursuant to the requirements of ASME Section XI, IWA-6000.

This completes our response to Confirmatory Issue #12.

Should additional information be required, please do not hesitate to contact us.

Sincerely,

/S$ a(Cf.

DLS/cb/02268607 l

See Attached Service Lint Copy to: T. E. Hurley, Regional Administrator NRC Region 1 L__

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cc: Troy B. Conner, Jr., Esq. 00CMcito Ann P. ikxigden, Esq. UiNRC Mr. Frank R. Romano Mr. Robert L. Anthony Ms. Phyllis Zitzer Charles W. Elliot, Esq.

I W 31 P2:32 -

.s Barry M. Hartman, Esq. FFicE 96 ., ..

Mr. Thmas Gerusky ME Tits g ,3,ti,lk, Dir'ector, Penna. Emergency. 8 RANCH Management Agency Angus R. Love, Esq.

David Wersan, Esq. \

Robert J. Sugannnn, Esq.  ;, ,

Kathryn S. Lewis, Esq.

d Spence W. Perry, Esq. -

day M. Gutierrez, Esq.

Atmic Safety & Licensing Appeal Board Atomic Safety & Licensing Board Panel Docket & Service Section -

Mr. E. M. Kelly  ?-

Mr. Timothy R. S. Canpbell 5

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<<uAhv cunne.wunum PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET 00ggD P.O. BOX 8699 PHILADELPHIA. PA.19101 '86 MAR 31 P2 :32 12158841 4000 (1 - ,.-

March 14, 1986~ - ~

Docket No. 50-352 Document Control Desk U.S. Nuclear Regulatory Commission Wachington, DC 20555

SUBJECT:

Licensee Event Report Limerick Generating Station - Unit 1 This LER concerns a failure of the Residual Heat Removal Sorvice Water System Effluent radiation monitors to meet a rcquirement of the Technical Specification.

References Docket No. 50-352 Report Number: 86-012 Revision Number: 00 Event Date: February 13, 1986 Report Date: March 14, 1986 Facility: Limerick Generati5g Station P.O. Box A, Sanatoga, PA 19464 This LER is being submitted pursuant to the requirements of 10 CFR 50.73(a)(2)(i)(B).

Very truly yours, W. T. Ullrich Superintendent Nuclear Generation Division cc: Dr. Thomas E. Murley, Administrator, Region I, USNRC E. M. Kelly, Senior Resident Site Inspector See Service List i

i . - - -

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  • l cc Troy B. Conner, Jr., Esq. 00gpf {0
  • Ann P. Hodgdon,' Esq.

Mr., Frank R. Romano -

, Mr. Robert L. Anthony '86 NAR 31 P2 :37~

. Ms. Phyllis Zitzer Charles W. Elliott, Esq. .,

Barry M. Hartman, Esq. [0g FiC , ,

Mr. Thomas Gerusky gggggy .

Director, Penna. Emergency Management Agency Angus Love, Esq.

David Warsan, Esq. **

Robert J. Sugarman, Esq.

Kathryn S. Lewis, Esq.

Spence W. Perry, Esq.

Jay M. Gutierre=, Esq. ,

Atomic Safety & Licensing Appeal Board Atomic Safety & Licensing Board Panel Docket & Service Section (3 Copies)

E. M. Kelly Timothy R. S. Campbell l '

l l

February 4, 1986 1

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, UCENSEE EVENT REPORT (LER) E'[*"dUs N "" **

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.. u a Limerick Generating Station - Unit 1 o,s,,,,,o,3,5,2f, jog , o teTL. ,4.

Failure of RHRSW System Rad Monitor Circuitry to Meet Technical Specifications a 1 a.i us. u. 6..... . ..., un in .... . e .u ...n . 6 u . .

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Abstract 86-012 - .. --

On February 13, 1986, while in Operational Mode 1 at 99.8% power, '

it was determined that all four rsdiation monitors on the Residual Heat Removal Service Water (RHRSW) system were not in ,

compliance with the Technical Specification Table 4.3.7.11-1, Note (1). The subject radiation monitors were not" capable of automatically isolating the RHRSW system in the event of a This capability had not been downscale failure of a monitor.

provided in the circuitry for the radiation monitors at the time of their installation.

All four monitors were declared inoperable and the appropriate ,

Action Statement was complied with by collecting grab samples A and >

analyzing them for gross radioactivity every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

modification has been completed installing the proper circuitry. ,

Ther~e were no adverse ef fects as a result of this condition.

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'"** *****.sa o w .a n c e ee LICENSEE EVENT REPORT lLER) TEXT C2NTINUATION l ta,38 . s/sima l

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Limerick Generating Station "" h UN #' E*' 'U '

Unit 1 '

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Mode 1 (Power Operation) -

Reactor Power (99.8%)

Description of the Event:

During a review of a revision to a surveillance test, it was .

dis _coverea that the installed circuitry of the Residual Heat l Removal Service Water (RHRSW) system effluent radiation monitors, although in compliance with the Final Saf ety Analysis Report (FSAR) Section 11.5, " Process and Effluent Radiological Monitoring and Sampling Systems", did not cause an automatic isolation of the RHRSW system in the event of a downscale failure '

of a radiation monitor as required by the Technical Specification Table 4.3.7.11-1 (Note 1) pages 3/4 3-101 and 3/4 3-102. ,

Although no automatic isolation occurred, the operator would have ,

been signaled of a downscale failure via an annunciator in the main control room and a pilot. light on the Logarithmic Count Rate -

Meter (LCRM), which is located in the Auxiliary Equipment Room.

  • l

_ Consequences of the Event:

There were no adverse consequences resulting from this conditilon.

l

! The poss'ible consequences of a failure to isolate the RHRSW l

system due to a downscale failure of the radiation monitors would l

have been minimal.

In the event of a downscale failure of one of the monitors, the operator would have been alerted via an annunciator in the I control room. Upon receipt of this alert, the appropriate action would have been taken, which may have included a manual isolation of the system. -

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? ac ,e.an 3 6a wJ. muc6tra E4!whalLCT Conseemsom LICENSEE EVENT REPORT ILER) TEXT CSNTINUATION annovas cas ao. sies-*i-

$1,satt stalk 5 eicius, . in eocur =w .in ui u a we.e s a iei eaes un Limerick Cenerating Station " ' "

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Cause of the Event:

r This isolated event was the result of an administrative oversight during the development of the surveillance test for this equipment and during the review of the Technical Specifications conducted pr.ior to receipt of the operating License.

Corrective Actions:

All four radiation monitors were immediately declared inoperable and the appropriate Action Statement entered; Technical Specification Table 3.3.7.11-1, page 3/4 3-100, Action 101 -

"With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that, at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, grab samples are collected and analyzed for gross radioactivity (beta or gamma) .... "

Modi fication No. 704, " Revise Output Circuitry of Selected LCRM Radiation Monitors", has been implemented in order to bring the system into compliance with the Technical Specification requirements.

A review was undertaken to determine if similar problems existed in other systems. This review revealed an additional problem with the RHRSW system. The "inop circuit failure" alarm feature had not been utilized as required on the RHRSW monitors. This feature provides a control room alarm and a RHRSW system effluent pathway isolation in the event of a circuit failure resulting from a low high voltage condition of a radiation monitor. The existing circuitry did provide isolation but did not provide a control room alarm in the event of an "inop circuit failure".

! This could have resulted in a system isolation which would not have been recognized as being caused by these radiation monitors.

Modification #704, mentioned previously, has also resolved this circuitry problem.

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LICENSEE EVENT REPORT ILER) TEXT CONTINUATION .mo.s e o. .o si.e-e =

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In addition, this review determined that the " circuit failure" alarm feature had not been utilized on theA Service Water Effluent '

Line radiation monitor (RISH-10-lK605). temporary circuit alteration has been made to make this feature functional and a permanent modification is scheduled to be implemented by April .

30, 1986.

Action Taken to Prevent Recurrence:

Implementation of the modifications identified as a result of the investigation will prevent recurrence.

Previous Similar Occurrences:

None.

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dtLAT ED CORRESPONDENCF PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 000KEJE0 5

PHILADELPHIA. PA.19101 m s'* * * '86 MAR 31 P2:32

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March 14, 1986

' LTF'CE C ' 'I '

Docket No. 56752[

3 '

Document Control Desk ._

U.S. Nuclear Regulatory Commission .~~

Waahington, DC 20555 -

SUBJECT:

Licensee Event Report .

Limerick Generating Station - Unit 1 This LER concerns a full reactor scram due to high neutron '

flux.

Reference:

Docket No. 50-352 Report Number: 86-011 Revision Number: 00 Event Date: February 10, 1986 Report Date: March 14, 1986 Facility: Limerick Generating Station P.O. Box A, Sanatoga, PA 19464 This LER is being submitted pursuant to the requirements of 10 CFR 50.73(a)(2)(iv). The submittal of this LER was dolayed as a result of the time necessary to. investigate the '

cause of the event. We regret any inconvenience the delay may hava caused.

Very truly yours,

,D h/'kJ$

W. T. Ullrich Superintendent Nuclear Generation Division cca Dr. Thomas E. Murley, Administrator, Region I, USNRC E. M. Kelly, Senior Resident Site Inspector See Attached Service List l

I

)

cc: Troy B. Conner, Jr., Esq. 00LKEiE0 gg Ann P. Hodgdon,' Esq.

Mr., Frank R. Romano Mr. Robert L. Anthony

. Ms. Phyllis Zitzer "DO' HM 31 P2:33 Charles W. Elliott, Esq. ,,

Barry M. Hartman, Esq. OFFICE O i *.

Mr. Thomas Gerusky 00CKETigGg Ti ,

Director, Pr. 9a. Emergency Management kgency

, Angus Love, Esq. s l David Wersan, Esq. *-

Robert J. Sugarman, Esq.

Kathryn S. Lewis, .Esq. ,

Spence W. Perry, E=q.

Jay M. Gutierrez, Esq. ,

Atomic Safety & Licensing Appeal Board Atomic Safety & Licensing Board Panel Docket & Service Section (3 Copies)

E. M. Kelly Timothy R. S. Campbell l

l February 4, 1986 l

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, UCENSEE EVENT REPORT (LER) Na8"8 ' $ Y " " " l

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Limerick Generating Station - Unit 1

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.. - . - - ..---.- na Abstract: 86-011 On February 10, 1986 at 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br /> with Unit 1 at 99.8 percent i

I rated power, a full reactor scram occurred as a result'of high

  • neutron flux (flow biased). The neutron flux sp*ike resulted from an increase in reactor pressure which was cansed by unexpected closure ,of the Turbine Control valves. A ground in the Electrohydraulic Control (EHC) circuit gaused the Titrbine Control valves to close. The cause for the ground is unknown, but suspected to have resulted from testing activity which involved temporarily connecting a digital-voltmeter in the circuit to monitor EHC signals. The consequences of the e. vent were minimal because the Reactor Protection System functioned -

as designed and automatically scr.ammed the reactor.

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    • '.' UCENSEE' EVENT REPORT ILER) TEXT CENTINUATION are ass a m as ooCati av aga ya g .m pagg g3 faCalf f maa.g g.g Lim 2 rick Generating Station "a le IE7 * *.if 001 0g2 or 0 l3 eisloleto1 3 i Sg 2l8 ; 6 ,-

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j Unit Conditions Prior to the Event: *

. I Mode 1 (Power Operation)

Reactor Power 99.8%

l Description of the Event:

I

- On' February 10, 1986 at 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br />, a full reactor scram occurred as a result of high neutron flux (flow biased). The l neutron flux spike was the result of an increase in reactor-pressure caused by the unexpected closure of the Turbine

  • Control valves.

The EIIS code for the affected system is JJ.

Consequences of the Events ,

The consequences of this event were minimal because the Reactor Protection System functioned as designed and automatically scrammed the reactor.

Cause of the Event:

The unexpected closure of the Turbine Control valves was caused by a ground in the load reference signal of the Turbine Electrohydraulic Control (EHC). The cause for the circuit ground is not confirmed but suspected to have resulted from I

taking final Startup Test Program related readings in the turbine EHC control cabinet. A digital-voltmeter (DVM) had.

been temporarily connected to the EHC circuit in order toIt was '

record EHC signals at 100 percent rated reactor power.

postulated that the circuit ground resulted from the DVM being connected to the EHC. Although the DVM was believed to be <

~

properly installed, an investigation of various DVM lead configurations, and scale and range settings was conducted.

During the investigation, the event could not be duplicated.

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8 a,s. 81 613146

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Corrective Actions: ,

The plant was stab'ilized following the scram and the EllC problem was investigated. The meter's connection in the circuit was investigated and found to be proper. The meter was then removed, tested, and found to operate properly. The unit-was returned to full power operation by 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> on February 12, 1986.

Action Taken to Prevent Recurrence:

A letter was issued to plant engineering staff requesting verification that all testing or troubleshooting activities are being controlled by applicable procedures and that no outstanding startup data acquisition activities, which lack formal approval, exist.

A memo was issued to control room supervision and operators to

  • re-emphasize their responsibility to evaluate the activities they approve for possible effects on plant operation.

Previous Similar Occurrences Limerick LERs85-049, 85-011,84-030, and 84-011.

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dELA1E.D COHRESPONDENCS PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET DOCK TED P.O. BOX 8699 PHILADELPHIA. PA.19101 '86 NAR 31 P2:32 (21518414000

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00CKLiiMarch 14, 1986

. . SRW)

Docket No. 50-352 Director Office of Resource Management US Nuclear Regulatory Commission Washington, DC 20555 ,

SUBJECT:

Limerick Generating Station Monthly Operating Report Gentlemen:

Enclosed is the monthly operating report for Limerick Unit 1 for the month of February, 1986, forwarded pursuant to Technical Specification 6.9.1.6.

Very t pyyour

/' ~ J/

R. H. Logue l Superintendent l

Nuclear Services Attachment .

cc: Director, Office of Inspection & Enforcement, USNRC (12 copies) l Dr. T. E. Murley, NRC E. M. Kelly, SeniorResidentSiteInsp(ctor Mr. David E. Ney, PA Dept. of Envir. Resources Mr. P. A. Ross, NRC (2 copies)

INPO Records Centhr See Attached licrvice List i

I

\- -

~ ~ _ . - .

cc: Troy B. Conner, Jr., Esq. Off[IC0 C

Ann P. Hodgdon,' Esq.

Mr. Frank R. Romano

. Mr.' Robert L. Anthony

. Ms. Phyllis Zitzer %6 WR 31 P2 33 Charles W. Elliott, Esq. .,

Barry M. Hartman, Esq. OfflCE cr - 4 00CMEriscY c Mr. Thomas Gerusky BRARv[' "-

Director, Penna. Emergency Management Agency Angus Love, Esq.

David Warsan, Esq.

Robert J. Sugarman, Esq.

Kathryn S. Lewis, Esq.

Spence W. Perry, Esq.

Jay M. Gutierrez, Esq. ,

Atomic Safety & Licensing Appeal Board Atomic Safety & Licensing Board Panel Docket & Service Section (3 Copies)

E. M. Kelly Timothy R. S. Campbell i

j February 4, 1986 l

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., DOCKET HD. 50 352 DATE MARCH 14, 1986 ,

COMPLETED BY PHILADELPHIA ELECTRIC COMPANY ,

.... ~ ...... .. ......

H.M. ALD EN l

'* EHEINEER.IN-CHARGE J

, LICENSING SECTION  !

> HUCLEAR GENERATION DIVISIGH TELEPHONE (215) 841-5021

~

  • OPERATING STATUS
1. WIT NAME LIMERICK WIT 1 l NOTESI WIT 1 INCUtRED Ch! l

.- . I 3 E. CEPORTING PERIOD 8 PEDRUARYe 1986 l AUTOMATIC SCRAM. I .,

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3. LICENSED THERMAL POWERitedTil 3t93 l l
4. HAMEPLATE RATING IGROSS PS4E18 1138 l i l t o
5. DESIGN ELECTRICAL RATING (HET t#4Els 1955* l l

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6. MAXDRAt DEPDCABLE CAPACITT (GROSS IS4Els 1992 I l 1 I
7. MAXIMUM DEPDE3ABLE CAPACITT INET 79dEls 1955 l l
8. IP CHANGED OCCtAt IN CAPACITT RATINGS (ITEMS HLASER 3 THROUGH 73 SINCE LAST REPORTe GIVE REASONSI On FebruaIy 1,1986 at 0001 henrs, the unit was elelved to be in ecuercial coe2 ation.
9. POWER LEVEL 70 letICH RESTRICTEDe IP ANY (HET MWEls
10. REASONS FOR RESTRICTIDHSe IF ANT 8 e

r THIS MONTH TR-TO-DATE CUMULATIVE I

l

11. Hotsis IN REPORTING PERIOD 671 672 672 ,,
12. HUMBER OF HOURS REACTOR HAS CRITICAL 651.1 651.1 651.1
13. REACTOR RESERVE SHUTDolef HOURS 0.8 0.0 0.0
13. HOURS GENERATOR CH-LINE . e45.6 645.6 645.6
15. L84IT RESERVE SHUTDOled HOURS
  • 0.0 0.0 0.0
16. GROSS THERMAL ENERET GENERATED lttell te109.974 EeIO9.974 2.109,974 5
17. GROSS ELECTRICAL ENERGY GFHERATED f tSaf) . 699.970 , 699.970 699.970 i . 18. HET ELECTRICAL ENERGT GENERATED (tSell 673.943 673e943 673.943
19. UNIT SERVICE FACTOR 96.1 96.1 96 1 O

a 0

0

St. UNIT AVAILA8ILITY FACTOR CS.1 96.1 96.1

, 21. WIT CAPACITT FACTOR IUSING Imc NET) 95.1 95.1 95.1

~ ~ . . . ..... -...- _... .,

22. WIT CAPACITT FACTOR (USING DER HETI 95.1 95.1 95.1
23. WIT FORCED OUTAGE RATE 3.9 li.9 3.9 .
24. SHUTD00445 SCHEDULES OVER NEXT 6 MONTHS (TTPE. DATE. AM3 OtNIATION OF I ACHit Unit 1 will be shutdown in May for suzvaillance testing and cjeneral rnaintenance newssary to onerate until the 1st W 14rg cutage. W
.u outage is expw.:ted to take six to eight weeks. ., -
25. IF SHUTD0644 AT EFO OF REPORT PERIDO ESTIMATED DATE OF STARTUPI
26. WITS TH TEST STATUS (PRIOR TO Cott'ERCIAL OPERATIDHit FORECAS't ACHIEVED .. ,

INITIAL CRITICALITT 12/19,84 12/12/8#.

l, INITIAL ELECTRICITT MID APRIL 85 4/13/85 .

.. _ ==. _

CotttERCIAL OPERATION IST QT4 86 t/01/86

.i -

8 8

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8 8 l

= . . .

. AVERAGE DAILY WIT POWE2 LEVEL DOCKET NO. 50 - 352 UNIT LIMERICK WIT 1 .

DATE ttARCH 14, 1964

. CortPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE LICEH3ING SECTION

, HUCLEAR GENERATIDN DIVI 5IDH .,

TELEPHONE I215) 641-5022 i!

MONTH FEBRUARY 1984 *.

5

?

DAY AVERAGE GAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL j[ tlWE-NET) (in4E-HET)

  • 1 1961 17 1050 2 1957 18 1049 3 1054 19 1056 4 1059 to 1958 5 1059 21 1965 6 1964 . 22 1955 7 1059 23 1960 t 4 1954 24 1960 J l 9 1865 25 1059 10 623 26 1953 11 85 27 1957 O,

w 11 950 28 1059 13 1940 I 14 1846 i

15 1074 .

. 16 1044

+ IA4IT SHUTDOWS Ape POWER REDUCTIONS DOCKET NO. 50 35E UNIT HAME LIMERICK UNIT 1 DATE MARCH I4e 1986 REPORT MONTH FEBRUARY 1986 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY, W.M. ALD EN

. ENGINEER.IH-CHARGE LICENSING SECTIDH HUCLEAR GENERATI0H DIVISIDH TELEPHONE (E15)*8'41-50EE

, I l l l l NETH00 0F l LICENSEE ISYSTEMICOMPONENTl CAUSE AM3 CORRECTIVE l ITYPElDWATIDHIREASONISHUTTIN3 DOWl EVENT l CODE l CODE l ACTION TO THO.l DATE l till (HOURSal (El l REACTOR (33 l REPORT 8 l (4) l (5) l PREVENT RECURRENCE

. I l l l l l l l l -

1 1 860E10 l Fl E6.4 l A l 3 l 86-11 1 HA I INSTRU l A FULL REACTOR SCRAM FROM 99.8% POWER. OCCUR:

l l l l l l l l l AS A RESULT OF HIGH HEUTR0H FLUX IFLOW t!ASE I I l l l l l l l THE HEUTROH FLUX SPIKE WAS A RESULT OF AN l I l l l l l l l INCREASE IN REACTOR PRESSURE CAUSED BY THE l l l l l l l l l UNEXPECTED CLOSURE OF THE TWBIHE CONTROL l l l l l l l l l VALVES. A GeotAm IN THE ELECTROHTDRAULIC l ,

1 I I I l l l l CONTROL (EHCl CIRCUIT CAUSED THE TURBINE l l I l l l l l l CONTROL VALVES TO CLOSE. THE CAUSE FOR THE l l l l l 1 l l l GROUFC IS IketHO W e BUT SUSPECTED TO HAVE l l l l l l l l l RESULTED FROM TESTING ACTIVITY W ICH INYOLVE l l l l l l l l l TEMPORARILY COWECTING A DIGITAL.VOLTt1ETER I l . l l l l l l l l THE CIRCUIT TO MONITOR EHC SIGHALS.

I I I ---- 1 I I I I I I I I E6.4 I I I I I I (Il (El (3) (4)

F - FORCED REASON METHOD EXHIBIT G . INSTRUCTION $ '

S - SCHEDULE 0 A . EQUIPMENT FAILURE (EXPLAIH) 1 - MAMJAL FOR PREPARATI0H OF DATA B . MAINTENANCE OR TEST E - MANUAL SCRAM. ENTRY SHEETS FOR LICENSEE C . REFUELING 3 - AUTONATIC SCRAQ. EVENT REPORT (LERI 0 - REGULATORT RESTRICTION 4 . OTHER IEXPLAINii FILE (HUREG-0161)

E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE (5)

S . OPERATIDHAL ERROR (EXPLAIH)

H - OTHERIEXPLAINI EXHIBIT I . SAME SOURCE 9

~ * * *

  • Dockot No. 50-352 Attachasnt to Monthly 1
Operating Report for February, 1986 Limerick Generating Station

', . Unit 1

! February 1 through** February 28, 1986 t

{ I. Narrative Summary of Operating Experiences , ,

, I

,l On February 1, 1986 at 0001 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, Limerick Generating

, Station Unit 1 was declared to be in commercial operation with a net capacity of 1055 MWe.

I On February 10, 1986 at 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br />, with the unit at 99.8%

I rated power, a full reactor scram occurred as a result of high neutron flux (flow biased). The neutron flux spike was the result of an increase in reactor pressure which was caused by the unexpected closure of the Turbine Control l! Valves. A ground in the Electrohydraulic Control (EHC)

,,:ll circuit caused the Turbine Control valves to close. The lt, cause of the ground is unknown, but suspected to have resulted from. testing activity which involved temporarily ll. ,

connecting a digital-voltmeter in the circuit to monitor

!: EHC signals. Reactor startup was begun the same day, the turbine-generator was synchronized at 1655 hours0.0192 days <br />0.46 hours <br />0.00274 weeks <br />6.297275e-4 months <br /> on February 11, 1986 and 100% rated power operation was

! achieved on February 12, 1986.

ii:

,g The unit ended the report period operating at 100% rated g

power.

i -

I !- II. Challenges to Relief Valves -

During this month, there were no challenges to the main - -
steam system safety-relief valves.

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