ML20199D149

Monthly Operating Repts for Oct 1997 for Byron Nuclear Power Station Units 1 & 2

ML20199D149
Person / Time
Site:	Byron
Issue date:	10/31/1997
From:	Kofron K, Vogl J COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BYRON-97-0269, BYRON-97-269, NUDOCS 9711200271
Download: ML20199D149 (8)

Text

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G>mmonwealth I dmin Company l  ;.~~ 11)ron bencrating Station l * *- 4 450 North Genrun Churt b Road

, H)ron, II,610ln4791 Tel HI 5-2,4 4 R11 November 11,1997 LTR: BYRON 97-0269 FILE: 2.7.200 U.S. Nuclear Regulatory Commission Washington, D C. 20555-0001 -

ATTENTION: Document Contro Desk

SUBJECT:

Monthly Ocerating Report Byron Nucir.ar Power Station, Units 1 and 2 NRC Docket Numbers: 50: 454 and 455 Gentlemen:

Enclosed for your information is the Monthly Operating Report covering Byron Nuclear Power Station for the period October 1 through October 31,1997.

Sincerely,

. d' l K. L, Kofron Station Manager Byron Nuclear Power Station KLK/JV/rp cc: A.B. Beach, Regional Administrator - Rlll G. Dick, Byron Project Manager - NRR v gh l Senior Resident inspector - Byron Office of Nuclear Safety -IDNS INPO Records Center B. Lewis, McGraw - Hill Nuclear Publications Dept.

9711200271 971031 PDR ADOCK 05000454

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BYRON NUCLEAR POWER STATION UNIT 1 AND UNIT 2 MONTHLY PERFORMANCE REPORT COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-454 NRC DOCKET NO. 050-455 LICENSE NO. NPF-37 LICENSE NO. NPF-66 (p t \ 97byritrs\ 97 0269.wpt-2)

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. OPERATIN3 DATA REPORT- l I

UNIT ONE DOCKET NO.- 050-454 UNIT NAME Byron One DATE 11/11/97 COMPLETED BY LVoal -

TELEPHONE f815) 234 5441 x2282 REPORTING PERIOD October.1997 (Month / Year)

MONTH YEAR TO DATE CUMLttATIVE 1

1. Design Electrical Rating (MWe-Net). I LThe nominal net electrical output of the unit specified l N/A I by the utility and used for the purpose of plant design.

• 120

, N/A

2. Maximum Dependable Capacity (MWe-Net).

The gross electrical output as measured at the output terminals of the turbine-generator during the most restrictive seasonal conditions minus the normal I

station service loads. 1,105 N/A N/A

3. Number of Hours the Raactor Waa Critical. l The total number of hours during the gross hours of the reporting period thtt the reactor was c.itical. 626.8 6,64P.S 88,535.1

4. Number of Hours the Generator Was On Une.

(Also called Service Hours). The total number of hours during ;he gross hours of the reporting period that the unit operated with breakers closed to the station bus. The sum of the hours the generator was on line plus the total outage hours should equal the gross hours in the reporting period. 619.9 6,596 87,684

5. Unit Reserve Shutdown Hours.

The total number of hours during the gross hours of

- the reporting period that the unit was removed from service for economic or similar reasons but was available for operation. 0 0 0

6. Net Ele..trical Energy (MWH).

The gross electrical output of the unit roeasured at the output terminals of the turbine-generator minus the normal station service loads during the gross hours of the reporting period, expressed in megawatt hours.

Negative quantities should not be used. 651,425 7,015,736 86,920,491 (pt\97byritts\970269.wp*-3)

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UNIT SHUTDOWNS ag  ;%

UNIT NAASEL Byron One DATE 11/11/97 CORAPLETED BY J Vool -

TELEPHONE (815)234-5441:

4 282 REPORTING PERIOD: October.1997

. (MontfWear) 1-

. TYPE DURATION REASON (1) METHOD OF CAUSF/ CORRECTIVE ACTIONS NO. DATE F: FORCED (HOURS) SHUTTING S: SCHEDULED DOWN (2) COMMENTS 125.1 A 1 Shutdown Unit Due To Valve 1StBSt9C Excessive Leakage 7 10/10/97 F L l

SUMMARY

Unit One was on-line for the rest of October.

(1) Reason (2) Method A - Equipment Failure (Explain) 1 - Manual B - Maintenance or Test - 2 - Manual TrpfScram C - Refueling 3- Automatic Trip / Scram D - Regulatory Restrictior' 4 - Conthuation E - Operator TrainingW Exarninaton 5 - Other (Explain)

F - Administrative G - Opr ational Error (Explain)

H - Other (Explain)

(pr\97byrltrs\970269.wpf-4)

= UNIQUE REPORTING REQUIREMENTS (UNIT 1)

, for the month of October,1997

, 1,

, Safety / Relief valve operations for Unit One. This information is provided pursuant to the reporting requirements contained in Technical Specification 6.9.1.8.

VALVES- NO & TYPE PLANT DESCRIPTION DATE_. ACTUATED ACTUATION CONDITION OF EVENT None

2. Licensee generated changes to ODCM.

Chapter 11: Remp sample locations were verified using a global positioning system and updated directions were documented.

Chapter 12: Added surveillance requirements and bases statemente for use and monitoring of the Old Steam Generator Storage Facility (OSGSF), and changed the LLD for tritium from 200 pCi/L to 2000 pCi/L to' maintain consistency with the NRC recommendations in Generic Letter 89-01.

3. Indications of failed fuel.

No. Fuel Reliability Indicator: FRl = 1.56 E-5 Ci/cc

4. L!censee Event Reports The following is a tabular summary of all Licensee Event Reports for Byron Nuclear Power Station, Unit One, occurring during the reporting period, October 1,1997 through October 31,1997. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.

Licensee Event Occurrence Report Number Date - Title of Occurrence 454: 97 016 10/07/97 Projected Steem Generator Leak Rate Combined with Technical Specification Limit for Dose Equivalent lodine Creates Potential for Operation Outside Design Basis.

454: 97-017 10/09/97 ENS Notification due to gas found in SI system during monthly vent.

454: 97-018 10/23/97 ECCS Venting 454: 97-019 10/28/97 Poten'ial failure of Westinghousa Fuel Rod Design Criterion.

454: 97-020 10/29/97 LER Required to address SGTR Analysis Assumptions.

454 97-021 10/28/97 Seismic Qualification Review not Performed Prior to Removal of ODSSD171.

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, OPERATING DATA REPORT UNIT TWO DOCKET NO. 050 455 UNIT NAME Byron Two DATE 11/11/97 COMPLETED BY J. Voal TELEPHONE (815) 234-54 11, x2282 REPORTING PERIOD October.1997 (Month / Year)

MONTH HAR TO DATE CUMULATIVE

1. Design Electrical Rating (MWe-Net).

The nominal not electrical output of the unit specified by the utility and used for the purpose of plant design. 1,120 N/A N/A

2. Maximum Dependable Capacity (MWe-Net).

The gross electrical output as measured at the output terminals of the turbine-generator during the most restrictive seasonal conditions minus the normal station service loads. 1,105 N/A N/A

3. Number of Hours the Reactor Was Critical.

The total number of hours during the gross hours of the reporting period that the reactor was critical. 470.7 S,911 78,433.7

4. Number of Hours the Generator Was On Line.

(Also called Service Hours). The total number of hours during the gross hours of the reporting period that the unit operated with breakers closed to the station bus. The sum of the hours the generator was on line plus the total outage hours should equal the gross hours in the reporting period. 466.6 6,880.7 77,727.3

5. Unit Reserve Shutdown Hours.

The total number of hours during the gross hours of the reporting ocriod that the unit was removed from service for economic or similar reasons but was available for operation. 0 0 0

6. Net Electrical Energy (MWH).

The gross electrical output of the unit measured at the output terminals of the turbine-generator minus the normal station service loads during the gross hours of the reporting period, expressed in megawatt hours.

Negative quantities should not be used. 488,536 7,460,360 76,752,331 (p r \ 97byrlt rs \ 97 02 69.wp f-6)

UNIT SHUTDOWNS ' '"

DOCKET NO. 050455 UNIT NAME- Byron Two DATE 11/11/97 COMPLETED BY J. Vool ~

TELEPHONE (815)234-5441 x2282 l

REPORTING PERIOD: October.1997 (Month / Year)

TYPE DURATION REASON (1) METHOD OF CAUSE/ CORRECTIVE ACTIONS NO. DATE F: FORCED (HOURS) SHUTTING DOWN (2) COMMENTS S: SCHEDULED 36 A 3 Rod Dr;.re Power Supply Failure Resulting in High Negative Flux Rate 6 10/10/97 F Reador T:'.o (LER 455: 97-003).

S 242.4 8 4 Replace Extraction Steam Bellows That Had Detenorated.

7 10/12/07 i

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SUMMARY

Unit Two was scheduled to come down for a Maintenance Outage to replace the extraction steam bellows. However, the reador trip occurred just prior to scheduled shutdown.

(1) Reason (2) Method A - Equement Fadure (Explain) 1 - Manual B - Maintenance or Test 2 - Manual Tripfwam C - Refueling 3 - Automate Trp/ Scram D - Regulatory Restriction 4 - Continuaten E - Operator Training /Ucense Examinaten 5 - Other (Explain)

F - Administ'atrve G - Operational Error (Explain)

H - Other (Explain)

(p:\97byrltrs\970269.wpf-7)

4 *

. , UNIQUE REPORTING REQUIREMENTS (UNIT 2) ,

for the month of October,1997 I

1. Safety / Relief valve operations for Unit Two. This information is provided pursuant to the reporting requirements contained in Technical Specification 6.9.1.8.

VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT None

- 2. Licensee generated changes to ODCM.

Chapter 11: Remp sample locations were verified using a global positioning system and updated directions were documented.

Chapter 12: Added surveillance requirements and bases statements for use and monitoring of the Old Steam Generator Storage Facility (OSGSF), and changed the LLD for tritium from 200 pCi/L to 2000 pCi/L to maintain consistency with the NRC recommendations in Generic Letter 89-01.

3. Indications of failed fuel.

No. Fuel Reliability Indicator FRI = 4.40 E 5 pCi/cc

4. Licensee Event Reports

' The following is a tabular summary of all Licensee Event Reports for Byron Nuclear Power Station, Unit Two, occurring during the reporting period, October 1,1997 through October 31,1997. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.

Occurrence Licensee Event Report Number Date Title of Occurrence 455: 97-003 10/10/97 U2 Reactor Trip and NRC Operations Center notification.

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