ML18094B255: Difference between revisions

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SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 89-036-00 January 17, 1990 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations lOCFR 50.73(a) (2) (iv). This report is required within thirty (30) days of discovery.
SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 89-036-00 January 17, 1990 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations lOCFR 50.73(a) (2) (iv). This report is required within thirty (30) days of discovery.
MJP:pc Distribution 9001300330 900117 PDR ADOCK 05000272 S PDC Sincerely yours, L. K. Miller General Manager -Salem Operations 0 . ts-2189 (SM) 12-88 NRC F0<m :Jee 19-831 U.S. NUCLE"R REOULATOAY  
MJP:pc Distribution 9001300330 900117 PDR ADOCK 05000272 S PDC Sincerely yours, L. K. Miller General Manager -Salem Operations 0 . ts-2189 (SM) 12-88 NRC F0<m :Jee 19-831 U.S. NUCLE"R REOULATOAY  
""'ROVED OMll NO. 3150....0104 LICENSEE EVENT REPORT (LER) EXPIRES: 8/31 II& F"CILITY NAME 111 Salem Generating Station -Unit 1 'DOCKET NUMIER 12) I 1;,i o 1s101010121112 1loF 013 TITLE 141 No. 13 Blowdown Automatic Isolation Due To Failure of The 1Rl9C RMS Channel EVENT DATE (151 LEA NUMBER Ill REPORT DATE 171 OTHER FACILITIES INVOLVED (II MONTH DAY YEAR YEAR k/  
""'ROVED OMll NO. 3150....0104 LICENSEE EVENT REPORT (LER) EXPIRES: 8/31 II& F"CILITY NAME 111 Salem Generating Station -Unit 1 'DOCKET NUMIER 12) I 1;,i o 1s101010121112 1loF 013 TITLE 141 No. 13 Blowdown Automatic Isolation Due To Failure of The 1Rl9C RMS Channel EVENT DATE (151 LEA NUMBER Ill REPORT DATE 171 OTHER FACILITIES INVOLVED (II MONTH DAY YEAR YEAR k/
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MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERISI 112 2 lo s 9 al 9 -316 -ol o ol 1 111 91 _o. OPERATING THll REPORT II SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFA &sect;: (Choclt OM or morw of th* fol/owing}  
MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERISI 112 2 lo s 9 al 9 -316 -ol o ol 1 111 91 _o. OPERATING THll REPORT II SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFA &sect;: (Choclt OM or morw of th* fol/owing}
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On December 20, 1989 at 0345 hours, during normal plant operations, the No. 13 Steam Generator (S/G) blowdown {WI} Radiation Monitoring System (RMS) {ILl channel, 1R19C, failed high. The channel failure caused isolation of No. 13 S/G Blowdown.
On December 20, 1989 at 0345 hours, during normal plant operations, the No. 13 Steam Generator (S/G) blowdown {WI} Radiation Monitoring System (RMS) {ILl channel, 1R19C, failed high. The channel failure caused isolation of No. 13 S/G Blowdown.
Previously, the 1R19C channel had been declared inoperable, on December 19, 1989 at 1150 hours, due to alternating illumination/clearance of the Control Room 1R19C channel fail light and periodic spiking of the radiation indication above the warning setpoint.
Previously, the 1R19C channel had been declared inoperable, on December 19, 1989 at 1150 hours, due to alternating illumination/clearance of the Control Room 1R19C channel fail light and periodic spiking of the radiation indication above the warning setpoint.
On December 19, 1989 at 1150 hours Technical Specification 3.3.3.8 Table 3.3-12 Action 27 was entered. It states: "With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10-7 microcuries/gram:  
On December 19, 1989 at 1150 hours Technical Specification 3.3.3.8 Table 3.3-12 Action 27 was entered. It states: "With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10-7 microcuries/gram:
: a. At least once per 8 hours when the specific activity of the secondary coolant is greater than 0.01 microcuries/gram DOSE EQUIVALENT I-131. B. At least once per 24 hours when the specific activity of the secondary coolant is less than or equal to 0.01 microcuries/gram DOSE EQUIVALENT I-131." S/G Blowdown Isolation is considered an Engineered Safety Feature. Subsequently, on December 20, 1989 at 0435 hours, the Nuclear Regulatory Commission was notified of the automatic actuation of SGBI in accordance with Code of Federal Regulations lOCFR 50.72(b) (2) (ii).   
: a. At least once per 8 hours when the specific activity of the secondary coolant is greater than 0.01 microcuries/gram DOSE EQUIVALENT I-131. B. At least once per 24 hours when the specific activity of the secondary coolant is less than or equal to 0.01 microcuries/gram DOSE EQUIVALENT I-131." S/G Blowdown Isolation is considered an Engineered Safety Feature. Subsequently, on December 20, 1989 at 0435 hours, the Nuclear Regulatory Commission was notified of the automatic actuation of SGBI in accordance with Code of Federal Regulations lOCFR 50.72(b) (2) (ii).   
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Revision as of 15:37, 25 April 2019

LER 89-036-00:on 891220,steam Generator 13 Blowdown Radiation Monitoring Sys Channel 1R19C Failed High,Resulting in Isolation of Steam Generator Blowdown.Caused by Equipment Failure.Detector Replaced & Channel calibr.W/900117 Ltr
ML18094B255
Person / Time
Site: Salem PSEG icon.png
Issue date: 01/17/1990
From: MILLER L K, POLLACK M J
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-036, LER-89-36, NUDOCS 9001300330
Download: ML18094B255 (4)
v • d • e


Text

  • Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 89-036-00 January 17, 1990 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations lOCFR 50.73(a) (2) (iv). This report is required within thirty (30) days of discovery.

MJP:pc Distribution 9001300330 900117 PDR ADOCK 05000272 S PDC Sincerely yours, L. K. Miller General Manager -Salem Operations 0 . ts-2189 (SM) 12-88 NRC F0<m :Jee 19-831 U.S. NUCLE"R REOULATOAY

""'ROVED OMll NO. 3150....0104 LICENSEE EVENT REPORT (LER) EXPIRES: 8/31 II& F"CILITY NAME 111 Salem Generating Station -Unit 1 'DOCKET NUMIER 12) I 1;,i o 1s101010121112 1loF 013 TITLE 141 No. 13 Blowdown Automatic Isolation Due To Failure of The 1Rl9C RMS Channel EVENT DATE (151 LEA NUMBER Ill REPORT DATE 171 OTHER FACILITIES INVOLVED (II MONTH DAY YEAR YEAR k/

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MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERISI 112 2 lo s 9 al 9 -316 -ol o ol 1 111 91 _o. OPERATING THll REPORT II SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFA §: (Choclt OM or morw of th* fol/owing}

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--ll0.73(11ll21Ulll LICENSEE CONTACT FOR THIS LEA (12) NAME TELEPHONE Nl/MBER AREA CODE M. J. Pollack -LER Coordinator COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DEICAllED IN THll REPORT 1131 CAUSE SYSTEM COMPONENT MANUFAC* TUR ER MANUFAC TUA ER B I IL DIE fT I y I I I I I I I I I I I I I . I I I I I I I I SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY YJ"R j YES (If yn, comp/or. EXPECTED SUBMISSION DATE} NO EXPECTED SUBMl$SION DATE 1151 I I I Aal'TRACT (Limit to 1400 1pocn, i.* .. opproximor.ly fifteon 1ingl1*1,,.c1 ry,,.wrlmn

/inn} (1111 On December 20, 1989 at 0345 hours0.00399 days <br />0.0958 hours <br />5.704365e-4 weeks <br />1.312725e-4 months <br />, the No. 13 Steam Generator (S/G) blowdown Radiation Monitoring System (RMS) channel, 1R19C, failed high. The channel failure caused isolation of No. 13 S/G Blowdown.

Previously, the 1R19C channel had been declared inoperable, on December 19, 1989 at 1150 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.37575e-4 months <br />, due to alternating illumination/clearance of the Control Room 1R19C channel fail light and periodic spiking of the radiation indication above the warning setpoint.

The root cause of the 1Rl9C channel failure has been attributed to an equipment The channel's detector and connector had failed. The 1Rl9C detector is a NaI Gamma Scintillator model LFE MD5C. The 1R19C detector and associated connector were replaced and a channel calibration successfully completed.

The channel was declared operable on December 21, 1989 at 2235 hours0.0259 days <br />0.621 hours <br />0.0037 weeks <br />8.504175e-4 months <br /> and Technical Specification Table 3.3-12 Action 27 was subsequently exited. NAC FDl'm :Jee (9-831 I *----*---* LICENSEE EVENT REPORT {LER) TEXT CONTINUATION Salem Generating Station Unit 1 -----------

DOCKET NUMBER 5000272 PLANT AND SYSTEM IDENTIFICATION:

Westinghouse

-Pressurized Water Reactor LER NUMBER 89-036-00 PAGE 2 of 3 ----==--*

Energy Industry Identification System {EIIS) codes are identified in the text as {xxl IDENTIFICATION OF OCCURRENCE:

No. 13 Stearn Generator Blowdown automatic isolation due to failure of the 1R19C Radiation Monitoring System channel Event Date: 12/20/89 Report Date: 1/17/90 This report was initiated by Incident Report Nos.89-783 and 89-784. CONDITIONS PRIOR TO OCCURRENCE:

Mode 1 Reactor Power 100% -Unit Load 1155 MWe DESCRIPTION OF OCCURRENCE:

On December 20, 1989 at 0345 hours0.00399 days <br />0.0958 hours <br />5.704365e-4 weeks <br />1.312725e-4 months <br />, during normal plant operations, the No. 13 Steam Generator (S/G) blowdown {WI} Radiation Monitoring System (RMS) {ILl channel, 1R19C, failed high. The channel failure caused isolation of No. 13 S/G Blowdown.

Previously, the 1R19C channel had been declared inoperable, on December 19, 1989 at 1150 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.37575e-4 months <br />, due to alternating illumination/clearance of the Control Room 1R19C channel fail light and periodic spiking of the radiation indication above the warning setpoint.

On December 19, 1989 at 1150 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.37575e-4 months <br /> Technical Specification 3.3.3.8 Table 3.3-12 Action 27 was entered. It states: "With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10-7 microcuries/gram:

a. At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microcuries/gram DOSE EQUIVALENT I-131. B. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 microcuries/gram DOSE EQUIVALENT I-131." S/G Blowdown Isolation is considered an Engineered Safety Feature. Subsequently, on December 20, 1989 at 0435 hours0.00503 days <br />0.121 hours <br />7.19246e-4 weeks <br />1.655175e-4 months <br />, the Nuclear Regulatory Commission was notified of the automatic actuation of SGBI in accordance with Code of Federal Regulations lOCFR 50.72(b) (2) (ii).

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 DOCKET-NUMBER 5000272 LER NUMBER 89-036-00

  • -------------
  • ----PAGE 3 of 3 The root cause of the 1R19C channel failure has been attributed to an equipment failure. The channel's detector and connector had failed. The 1R19C detector is a NaI Gamma Scintillator model LFE MDSC. Initial investigation of this event identified a bad high voltage cable connector.

After replacing the cable connector, a channel caiibration was conducted.

The calibration identified the detector as not performing to its full capabilities.

Channel calibration of the 2R1A channel is performed quarterly in accordance with manufacturers recommendations.

The calibration was last prior to this event, on September 27, 1989. It was scheduled to be done January 3, 1990. ANALYSIS OF OCCURRENCE:

The 1R19 RMS channels monitor S/G blowdown water from the individual S/Gs for radioactivity.

An alarm of this channel may indicate a significant primary to secondary leak. The alarm setpoint is set at a release rate which is less than the limits set by the Technical Specifications and the Updated Final Safety Analysis Report. Upon receipt of a channel alarm indication, the SGBI valve (GB4), for the respective S/G, will automatically close, resulting in SGBI. During this event the No. 13 SGBI GB4 valve closed as designed.

The Condenser Air Ejector radiation monitor is used as the corroborating channel for the 1R19 radiation monitors.

However, an alarm from this channel would not identify the specific S/G where a primary to secondary leak has occurred.

A review of this event has shown that the 1R19C alarm was not actuated due to high radiation levels in the No. 13 S/G blowdown line. Therefore, the health and safety of the public was not affected by this event. However, since SGBI is considered an ESF system, this event is reportable in accordance with Code of Federal Regulations lOCFR 50.73(a) (2) (iv}. CORRECTIVE ACTION: The 1R19C detector and associated connector were replaced and a channel calibration successfully completed.

The channel was declared operable on December 21, 1989 at 2235 hours0.0259 days <br />0.621 hours <br />0.0037 weeks <br />8.504175e-4 months <br /> and Technical Specification Table 3.3-12 Action 27 was subsequently exited. k:tte...:i&v General Manager -Salem Operations MJP:pc SORC Mtg.90-006

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