ML20090D846

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Annual Operating Rept for 1991
ML20090D846
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 12/31/1991
From: Cottle W
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GNRO-92-00014, GNRO-92-14, NUDOCS 9203090080
Download: ML20090D846 (12)
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3:5 ENTERGY W. T Cottle February 28, 1997 U.S. Nuclear Regul atory Conrnissior, Mail Station P1-137 Washington, D.C. ?O555 Attention: Document Control Desk

SUBJECT:

Grand Gulf Nuclear Staticn Unit 1 Docket No. 50-416 License No. NPf-29 1991 Annual Operating Report GNRO-92/00014 Gentlemen:

Entergy Operations, Inc. is transmitting the Grand Gulf Nuclear Station (GGNS) Unit 1 Annual Operating Report for 1991. This report is in accordance with the reporting program described in Regulatory Guide 1.16, Revision 4, Part C.1.b as modified by the NRC letter to GGNS dated May 25, 1987 (MAEC-87/9131).

Provided as attachments are:

1. A narrative summary of operating experience during the year -

1991,

2. Main Steam Line Safety Relief Valve challenges,
3. A tabulated annual report of personnel exposure greater than 100 mrem /yr, end
4. A s:mmary of failed fuel indications / inspections.

Yours truly, wr@C WTC/TKM/cg attachments:

cc: (See Next Page) ,

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s February 28 1992 GNRO-92/00014 Page 2 of 3 cc: Mr. D. C. Hintz (w/a)

Mr.

Mr. R.J.

B. Mathis McGehee (w/a)

(w /a)

Mr. N. S. Reynolds (w/a)

Mr. H. L. Thomas (w/o)

Mr Stewart D. Ebneter (w/a)

Re lonal Administrator U.^. Nuclear Regulatory Commission Region 11 '

101 Harietta St., N.W., Suite 2900 Atlanta, Georgia 30323 Mr. P. W. O'Connor, Project Manager (w/a)

Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Conrission Mail Stop 13H3 Washington, D.C. 20555 i

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At t achment i to GNKO-92/0001I.

Pap 1 of 2 Sumary of Operating Experience 1991 lhe following is a sunnary of Grand Gulf Nuclear Station (GGNP Unit 1 operating experience for the 1991 calendar year. During 1991, the reactor was critical for 8,230.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> with the generator on line for 8036.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.

On february 13, 1991, a runback of Reactor Recirculation flow Control Valve "A" occurred. This corresponded to a 14% reactor power reduction.

The problem was traced to a circuit card which was replaced and retested.

The plant returned to 100N power two hours after the event.

On March 8, 1391, reactor power was reduced to 70% at the request of the system dispatcher.

lhe plant had been on-line 96 consecutive days prior to a reactci scram which occurred on April 6, 1991 (LER 91-002-01), during the Automat.c lurbine Testing (All) Turbine Overspecd Trip Test hurvei'. lance. The scram was due to f ailure of the test circuitry poner supnh module, which causcd a main turbine trip, lhe module was replaced and the generator was synchronized at 1603 hours0.0186 days <br />0.445 hours <br />0.00265 weeks <br />6.099415e-4 months <br /> on April 7, 1991.

Reactor power was decreased to 6?% on April 30, 1991 to perform an investigation cf an increase ;n Steam Tunnel temperature. :t was determined that a reactor water cleanup instrument line and a flow element gasket were leaking and reactor power was reduced to 50% on May 1 for the repair activity. Reactor power was returned to 100% on May 3, 1991.

During a controlled shutdown on June 11, 1991 to reolace the recirculation pump seals, the reactor stranned at 1840 hours0.0213 days <br />0.511 hours <br />0.00304 weeks <br />7.0012e-4 months <br /> (LER 91-004). The scram was caused by a loss of condensate /feedwater flow resulting from condensate minimum flow control valve failure. New seals were installed on "A" and "C" reactor recirculation pumps and the generator was synchronized at 0856 hours0.00991 days <br />0.238 hours <br />0.00142 weeks <br />3.25708e-4 months <br /> on June 16, 1991.

On June 17, 1991 at 0935 hours0.0108 days <br />0.26 hours <br />0.00155 weeks <br />3.557675e-4 months <br />, the unit tripped as a result of a "B" phase 500 kV sw;tchyard circuit breaker ground fault and subsequent service transformer lockout (LER 91-005-01). Corrective actions were taken and the generator was synchronized June 19, 1991 at 0421 hours0.00487 days <br />0.117 hours <br />6.960979e-4 weeks <br />1.601905e-4 months <br />.

On June 25, 1991, a OlV 11 RWCU isolation occurred due to a voltage surge resulting from a lightning strike to an incoming 500 KV line (LER 91-006).

The RWCU system was reset and RWCU pumps restarted.

On July 28, 1991, the reactor scrammed from a Turbine Control Valve (TCV) fast closure due to load shed of BOP buses (LER 91-007). A design fault was found in LSS panels, The Division I and 11 LSS panels were modified and the generator was synchronized August 6, 1991 at 2013 hours0.0233 days <br />0.559 hours <br />0.00333 weeks <br />7.659465e-4 months <br />.

The teactor scrammed from 100% power August 10, 1991 at 1906 hours0.0221 days <br />0.529 hours <br />0.00315 weeks <br />7.25233e-4 months <br /> (LER 91-010). This scram was caused by a lightning induced Spike on ApRMs.

The generator was synchronized August 12, 1991 at 0649 hours0.00751 days <br />0.18 hours <br />0.00107 weeks <br />2.469445e-4 months <br />.

AL'nPERRP/SCMPFLR - 4

Attachment I to GNR9-92/ooo14  !

Page 2 of 2 i 4 +

t Sumary of Operating Experience 1991 The plant had been on line 99 days when an automatic reactor scram occurred November 19, 1991 (LER 91-012). The scram was a result of an APRM spike due to a lightning strike. A task force investigated Grand ,

-Gulf's susceptibility to lightning strikes. The generator was synchronized at approximately 2310 hours0.0267 days <br />0.642 hours <br />0.00382 weeks <br />8.78955e-4 months <br /> on November 23.

On December 6, 1991, the Division II LSS Panel aower supply failed. The 15 and 24 volt power supplies were replaced. 11e panel was retested and restored to operable status.

On December 29, 1991 power was reduced to cold shutdown for replacement of "B" ktcirculation Pump Shaft. 821-F80'l feedwater check valve f ailed its leak check surveillance. This valve was inspected and work completed.

During systen, realignment, valve E124004A would not stroke due to thermal binding. Reactt,r coolant temperature was decreased and the valve was successfully opened. The plant returned to power January 10, 1992.

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At t achnient 11 to GNRO-92/00014 l'ap,e 1 el 3 HAIN STEAM SAFE 1Y REllEr val.VE CliAl.,lENGES 1991 This section contains a summary of mairi steam li' eafety relief valve challenges which occurred during 1991 as reportet the GGNS lionthly Operating Reports for that period.

The sunnaries were originally included in the following monthly reports:

June IN 1 Report -

GNRO-91/00121 - dated: July _103 _1991 July 1991 Report -

GNRO-91/00144 - dated: August 14, 1991 ANoPERRP/SCMPFLR - 7

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At techment 11 t.o GNRO-92/00014 l Page 2 of 3 1

MAIN STEAM SAFETY REllEF VALVE CHALLENGES 1991 i 00CKLT NO. _50 _416.. .

3 COMPLETED BY T. K. Murray 1ELEPHONE TMI D 37 T40T' Date of Occurrence: June 17, 1991 _ _

Plant Operating Condition:

Rx Thennal Power 7],.7,3 P.x Pressure (psig) 999_ Rx Mode 1 Rx Powcr (MWE) _862_ Rx Temperatures 540 F Number of mainsteam line SRVs: 20 _

Number of SRVs affccted by event _5 Narrative:

On June 17, 1991, a ground fault on the B Phase of Circuit Breaker J1532 caused a lock out on Service Transformer 11.

There were no automatic SRV actuations. These SRVs were manuelly operated: SRV B21-f041K actuated 3 times. The following SRVs actuated once: 821-f 0510, B21-F041E, B21-f047L and B21- F0470.

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. 1 At tachtnent 11 to GNRO-92/00014 Page 3 of 3 MAIN STEAM SAFETY RELIEF VALVE CHALLENGES 1991 DOCKET NO. ~~

50-416 UNIT 1 COMPLETED BY 7. K. Murray TELEPHONE TiiUTTT1FF40T Date of Occurrence: July 282 1991 , , , _ , _ , _ _

Plant Operating Condition:

Rx Thermal Power 100't Rx Pressure (psig) 104ft.7 Rx Mode 1 Rx Power (MWE) I??0 Rx ;emperatures 540 f Number of mainsteam line SRVs: 20 Number of SRVs affected by event: 11 Narrative On July 28, 1991, a reactor scram occurred from lurbine Control Valve fast closure due to loss of power to the turbine control fluid pumps (EllC) . The loss of power resulted from an inadvertent Division 11 L.SS load shed.

The following SRV's actuated automatically once:

821-f047A B21-f04/C, B21-f0470, B21-f047G, 821-IO47H. 821-f047L, B21-f051A, B21-f051B, B21-f0510, B21-f051F, and B21-f051K.

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i Attachment 111 to GNRO-92/00C14 Page 1 of 4 j GGNS tlNIT 1 ANNUAL REPORT MAN-REN EXPOSURE -_1991 This section contains a tabulation of the number of station, utility and other personnel receiving exposures greater than 100 mrem /yr and their associated Man-Rem exposure according to work and job function. Also included is a tabulation of the number of personnel by exposure range.

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  • At t ac hinen t 111 to GNim-92/00014 Page 2 of 4 IW1(kli Of-[El.110hl, Ikt.

r(RS0nt(L A4 #AN 6(R If W00144 HIT FL*(!!0N FlhAL !4 0F TH( f( A& ill0RT (CR 1991 EP$[R OF FIE!0HIL OVit 100 *FP 1014 stW i[M STA110N Uilitif CCattAC1 Elplis Sini!CN 11tlLif f (CatlACI pkq65

[PPL0fttS taPL0fl1$ A4 01F(FS tu'ltit!ti (*PL0 fill 64 Dirt 65 L(ACICROFS/HtVIILL8kCE nalkffh8=C( 5 0 0 0.032 0.M 0 0.000 CFIRAf!CAS 52 0 t 12.039 0. H0 0.!ff HEALTH hfSICS 36 0 4 R.507 0.000 1.336

$0t[FVISDRf 5 0 1 0.M 6 0.0(0 0.026 (41WilR14 3 0 1 0.219 0. H 0 0.002 FHllN( *A!Ni[sAdl MAlb1(NA*CE 128 0 59 30.647 0. 0 % 20.992 Ot[RA110NS 14 0 3 0.407 0.000 0.061 PLALTH h fS!CS 29 0 2 4.096 0.000 0.344 SLTDylHRY 6 0 1 1.002 0.0 H 0.220 DGINttRINL 2 0 1 0.241 0.000 0.113

!W SIAVICI INSFICf!0N aAINi[NANC[ 0 0 0 0. H0 0.H0 0.000 0FilAfl045 0 0 0 0.000 0.H0 0.0 H N(Al!H NV$1CS 0 0 0 0. H0 0, H 6 0. 0H SDr[RVISORT 0 0 0 0. H0 0.000 0.000 (41N[Dl4 0 0 < 0.0 H 0.000 0.H0

$PICIAL aAINltNANCf plWitHNCE 6 0 0 0.000 0.000 0.000 0F[RA110NS 0 0 0 0.000 0.000 0. 0 H WCAL1W N f51C$ 0 0 0 0. H 0 0.000 0. 0 H SUFrkVIS0kT 0 0 0 0. H0 0.0H 0.0H Ptikt[R14 0 0 0 0.000 0.H0 0.0(0

  1. SitF10 CESSING MAlkitNhtE 49 0 6 1.794 0.000 0.298 0FifA110NS 1 0 6 0.643 0.000 1.683 WIALTH N YSICS 7 0 1 2.167 0.000 0.002 SLffERVIS0kT 0 0 0 0.000 0.000 0. H0 (41NI(Fl4 0 0 0 0.000 0.C H 0.0H Rif tl!Ll4 4Al%1[NAkCE 0 0 0 0.000 0.000 0.000 0FDAi!0NS 0 0 0 0.000 0.CH 0.0H NEALTH h tSICS 0 0 0 0.0 H 0.H 0 0.000

$UFIRV150RY 0 0 0 0.0H 0.000 0.000 E%!4(R14 0 0 0 0.0H 0.000 0.000 101Alf FAINi[ NAN ([ 202 0 67 40.47$ 0.000 21.276 0F(RA110NS 67 0 14 13.289 0. 0H 1.932 NEAlfH NTSICS 72 0 7 14.7M 0.0H 1.752 CUitRVISORT  !! 0  ? 1.288 0. 0H 0.244 (41N((R14 t 6 2 0.460 -0.000 0.115 GRA4 1014L 357 0 92 7 .JH / [ 0.H0 2$.321

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.j gb,p.W.1;2 Rhs.das4reteettoMdafer hte General Manager GLWS hte

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. CNTERGY OPERATIONS, INC. At tachment 111 to c"l:0 92/00014 Page 3 of 4

SUMMARY

OF PERSONNEL MONITORING REPORT

. FINAL END Ol* THE YEAR REPORT POR 1991 Number of Estimate 6 whole body exposure range individuals in each range No Monsurable Exposure ................................................ 1396 Loss than 0.1 ......................................................... 425 0.1 to 0.25 ....................................................... .. 126 0.25 to 0.5 ........................................................... 99 0.5 to 0.75 .......................................................... 32 0.75 to 1.0 ........................................................... 10 1.0 to 2.0 ........................................................... 4 2.0 to 3.0 ........................................................... 3 3.0 to 4.0 ........................................................... 0 4.0 to 5.0 ........................................................... 0 5.0 to 6.0 ........................................................... 0 6.0 to 7.0 ........................................................... 0 7.0 to 8.0 ........................................................... 0 8.0 to 9.0 ........................................................... 0 9.0 to 10.0 .......................................................... 0 10.0 to 11.0 .......................................................... 0 11.0 to 12.0 .......................................................... 0 12.0 and over ......................................................... 0 Total number of personnel monitored 2095 (1) True Total Dose ( REM ) 93.968 (1) Average REM per person 0.343 A _.

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~" General ~{pManager GGNR S ,_Q.10 -9'9 Tate Rfdigtl'on Protecti Q Manager ~~'Uate (1) Excluding 1821 persons with less than 0.1 REM. Total Dose on site for 1991 t is 104.901 Rem for a11' persons monitored.

o Attachment 111 to GNRO-92/00014 Page 4 of 4 0 .

Special Maintenance Activities There were no special maintenance activities in 1991.

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. -1 Atiachment IV to GNRO-92/00014 a.

Pago 1 of i

SUMMARY

Of FAILID FUEL INDICATIONS /INSPECil0NS l l

,- No irradiated fuci assembly examinations were performed during the l reporting )eriod; however, one fuel rod failure is estimated f rom Cycle 5  ;

- fuel relia)ility data. No Technical Specification limits have been  !

exceeded. '

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