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| issue date = 01/04/1994
| issue date = 01/04/1994
| title = LER 93-019-00:on 931203,TS Action Statement Entered Due to Waste Gas Holdup Sys Oxygen Concentration Being Greater than 2% for More than 48 H.Oxygen Concentration within Waste Gas Sys Reduced to Less than 2% on 931212.W/940104 Ltr
| title = LER 93-019-00:on 931203,TS Action Statement Entered Due to Waste Gas Holdup Sys Oxygen Concentration Being Greater than 2% for More than 48 H.Oxygen Concentration within Waste Gas Sys Reduced to Less than 2% on 931212.W/940104 Ltr
| author name = PASTVA M J, VONDRA C A
| author name = Pastva M, Vondra C
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| addressee name =  
| addressee name =  
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:.. . e PStiG *Public Service Electric arid Gas Company *P.O. Box 236
{{#Wiki_filter:..               .                 e PStiG
* Hancocks Bridge: New Jersey 08038 * . Salem Generating Station u. s. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555.  
      *Public Service Electric arid Gas Company *P.O. Box 236
* Hancocks Bridge: New Jersey 08038 *
      . Salem Generating Station January 4, 199'} t./
: u. s.       Nuclear Regulatory Commission Document Control Desk Washington, DC               20555.


==Dear Sir:==
==Dear Sir:==
SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT*93-019-0b.
SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT*93-019-0b.
January 4, 199'} t./ This Licensee Event Report is being submitted pursuant to the . requirements of Code of Federal Regulation lOCFR50.73(a)
This Licensee Event Report is being submitted pursuant to the                                 .
(2) (i)(B). This report is required to be issued within thirty (30) days of event discovery.
requirements of Code of Federal Regulation 10CFR50.73(a) (2) (i)(B).
MJPJ:pc Distribution 9401310028 940104 PDR ADOCK 05000272 S PDR TherxJ'i\'cr is 11; your hands. l Sincerely yours, i ' I . 95*2189 REV 7-92 l NRC FORM-366 (6-891 U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104  
This report is required to be issued within thirty (30) days of event discovery.
.. LICENSEE EVENT REPORT (LERI EXPIRES: 4/30/92 .ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT-BRANCH (P-530). U.S. NUCLEAR REGULATORY COMMISSION.
Sincerely yours, MJPJ:pc Distribution 9401310028 940104               ~*
WASHINGTON.
PDR ADOCK 05000272 S                         PDR   l  i I
DC 20555. AND TO THE PAPERWORK REDUCTION PROJECT 13150-01041, OFFICE OF MANAGEMENT AND BUDGET. WASHINGTON, DC :20503. FACILITY NAME (11 I DOCKET NUMBER 121 I PAGE 131 Salem Generating Station--Unit 1 o 15IoIoIo12 I 712 1 loF 0 14 TITLE (41 Waste Gas Holdup System Oxygen Concentration Greater Than :z% For More Than 48 Hours. EVENT DATE (51 MONTH DAY ii 2 ol 5 OPERATING MODE (91 YEAR 9 3 5 0 0 LER NUMBER 161 REPORT DATE (71 OTHER FACILITIES INVOLVED (Bl YEAR \?? SEQUENTIAL it\ REVlSION MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERISI NUMBER NUMBER o1s1010101 I 913 -ol 1 19 -o lo 0I1 ol4 9[ 4 0 1 5 IO J.O I O I I THIS REPORT IS SUBMITTED PURSUANT TO THE OF 10 CFR §: (Ch*_ck ono or moro of th* fo/low;ngJ 1111 20.402(bl 20.405lcl 60.73l*ll2Hivl 73.71lbl -,_ ,___ 20.405(o)(1llil  
TherxJ'i\'cr is 11; your hands.
..__;_ 50.36(cll1l 60.73_(*11211*1 73.71 lcl -,___ ,___
                                                                                                    . 95*2189 REV 7-92
50.36lcll21 60.7311l121(vii)
 
OTHER !Specify in Absrrocl I I .-.--,___ -btJ/ow tJnd in T1Jxt, NRC Form ' ,,,. 20.4051o)(1 lliiil x 50.731*ll2llil 50.7311H2llviiil!AI
l NRC FORM-366                                                                                                                 U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104 (6-891
-366AJ -;-.-. """* ....... -,___ 50.7311)(2)(iil 60.7311l12)(viiillBl
                                                                          .                                                                                                                                                     EXPIRES: 4/30/92
,___ ,___ 50.7311)(2)(iiil 60.7311l12llxl
                                                                                                                                                                                                        .ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD LICENSEE EVENT REPORT (LERI                                                                                            COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT- BRANCH (P-530). U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON. DC 20555. AND TO THE PAPERWORK REDUCTION PROJECT 13150-01041, OFFICE OF MANAGEMENT AND BUDGET. WASHINGTON, DC :20503.
[''"\"'"?''\'")""\{"-")"(){)"")""{)J--J 20.40511)(1  
FACILITY NAME (11                                                                                                                                                                                                 DOCKET NUMBER 121                     I       PAGE 131 Salem Generating Station-- Unit 1 TITLE (41 Io 15IoIoIo12 I 712                     1   loF 0 14 Waste Gas Holdup System Oxygen Concentration Greater Than                                                                                                                                       :z%   For More Than 48 Hours.
)(iv)* ['}:(\: ::::::.:-:  
EVENT DATE (51                                                                 LER NUMBER 161                                 REPORT DATE (71                                                 OTHER FACILITIES INVOLVED (Bl MONTH                    DAY                        YEAR                  YEAR
.; .. ,., "" 20.40511ll111vl  
                                                                                      \??   SEQUENTIAL NUMBER    it\ REVlSION NUMBER MONTH                     DAY                   YEAR                 FACILITY NAMES                     DOCKET NUMBERISI o1s1010101                   I     I ii    2 ol 5                                  9 3 913 -                               ol 1     19 -   o lo           0I1                     ol4                   9[ 4                                                     0 1 5 IO J.O I O I           I    I THIS REPORT IS SUBMITTED PURSUANT TO THE R~OUIREMENTS OF 10 CFR                                             §: (Ch*_ck ono or moro of th* fo/low;ngJ 1111 OPERATING MODE (91 5                  20.402(bl                                     20.405lcl                                             ,_      60.73l*ll2Hivl                       ,___  73.71lbl 20.405(o)(1llil                               50.36(cll1l                                                   60.73_(*11211*1                           73.71 lcl 0 0                        2~.40511)(1)(iil                              50.36lcll21
,* .... *' '...... ,* :* ,* .* ,* ,*: .. ' ;* ;* LICENSEE CONTACT FOR THIS LER (121 NAME TELEPHONE NUMBER AREA CODE M. J. Pastva, Jr. -LER.Coordinator COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN *THIS REPORT 1131 :*:* :*:-:**:*::*:*:.;
                                                                                                                                                                                      ,___      60.7311l121(vii)                         OTHER !Specify in Absrrocl
.. ;.;.;.::*:-:*:*:*
                                                            .-.-                                                     - x btJ/ow tJnd in T1Jxt, NRC Form
CAUSE SYSTEM COMPONENT i:::: "\: :::::,:Y::?:F CAUSE SYSTEM COMPONENT
[''"\"'"?''\'")""\{"-")"(){)"")""{)J--J
:-:* *:*:*:*: :-:* :-:* :-:-*:*: :-:-::: :-:* -:-: I I I I I I I :-:* :-:* -:-: I I I I *:*: }: :} :::::::r ;::: -:-:-:::::;:;::;::-:*  
                                                            ,,,.                  20.4051o)(1 lliiil 20.40511)(1 )(iv)*
-:-:-:*:*
                                                                                                                    -,___        50.731*ll2llil 50.7311)(2)(iil 50.7311H2llviiil!AI 60.7311l12)(viiillBl
I I I I I I I -:-:::;:;:::
                                                                                                                                                                                                                      '                - 366AJ
:-:*::::::::::;:.,., *:*:* I I I I SUPPLEMENTAL REPORT EXPECTED 1141 (If v*s. comp/*<* EXPECTED SUBMISSION DATE! ABSTRACT (Umii to 1400 spaces, i.ll., approximately fifrsen single-space rvpewrirren lines) (16) TURER I I I I I I EXPECTED SUBMISSION DATE 1151 MONTH DAY YEAR I I I oxygen (0 2) concentration within the waste Gas Holdup System was > 2% for > 48 hours. On 12/3/93, at 0910 hours, Technical Specification (TS) Action Statement 3.11.2.5.a.
['}:(\:               ::::::.:-:       .; .. ,.,               ""               20.40511ll111vl                               50.7311)(2)(iiil                                              60.7311l12llxl
was entered due to o 2 concentration of
            ,* .... ~* *' '......   ,* :*     ,* .* ,* ~.;  ,*:..' ;* ;*
* 2.17% by volume in 13 Waste Gas Decay Tank (WGDT). Efforts to reduce the concentration to < 2% were implemented  
LICENSEE CONTACT FOR THIS LER (121 NAME                                                                                                                                                                                                                               TELEPHONE NUMBER AREA CODE M. J. Pastva, Jr. - LER.Coordinator COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN *THIS REPORT 1131 CAUSE              SYSTEM                              COMPONENT                      M~~~~~C-       R~6&deg;~~:g;E i:::: "\:                 :::::,:Y::?:F               CAUSE SYSTEM       COMPONENT
.. -o 2 concentrations above were subsequently measured in other WGDTs; 3.04% in 11 WGDT on 12/8/93, .3.11% in 14 WGDT on 12/8/93, and 3.29% in 12 WGDT on 12/9/93. _The maximum o 2 concentration was 4.25% in 13 WGDT on 12/4/93. The root cause is attributed to "Design, Manufacturing, Construction/
                                                                                                                                                                                                                      'MANUFAC-TURER I                         I             I     I         I     I     I                                                         *:*:                 I            I    I    I         I   I   I
Installation", as per NUREG-1022.
:::::::r
The source of the o is attributed to routine refueling/
                                                                                                                              }: :}:-:-:::::;:;::;::-:* -:-:-:*:*
maintenance outage fn addition, extensive modifications to the Waste Gas Analyzer and Waste Gas System were performed requiring these systems be opened. Prior to closure, steps were performed to purge these systems with nitrogen *. However, the design of these systems does not lend itself to effective purging. Furthermore, the calibration of the Waste Gas Analyzer introduced additional o 2 into the system. This was further due to the fact that the online o 2 analyzer was out of service for replacement.
I                         I I I                           I     I     I                                                                             I            I    I    I         I   I   I SUPPLEMENTAL REPORT EXPECTED 1141                                                                                                               MONTH        DAY      YEAR EXPECTED
                                                                                                                                          ~NO SUBMISSION DATE 1151
~YES                  (If v*s. comp/*<* EXPECTED SUBMISSION DATE!
I          I        I ABSTRACT (Umii to 1400 spaces, i.ll., approximately fifrsen single-space rvpewrirren lines) (16) oxygen (0 2 ) concentration within the waste Gas Holdup System was > 2%
for > 48 hours. On 12/3/93, at 0910 hours, Technical Specification (TS)
Action Statement 3.11.2.5.a. was entered due to o 2 concentration of
* 2.17% by volume in 13 Waste Gas Decay Tank (WGDT). Efforts to reduce the o~ concentration to < 2% were implemented ..- o 2 concentrations above 2~ were subsequently measured in other WGDTs; 3.04% in 11 WGDT on 12/8/93, .3.11% in 14 WGDT on 12/8/93, and 3.29% in 12 WGDT on 12/9/93.
_The maximum o 2 concentration was 4.25% in 13 WGDT on 12/4/93. The root cause is attributed to "Design, Manufacturing, Construction/
Installation", as per NUREG-1022. The source of the o is attributed to routine refueling/ maintenance outage activities~ fn addition, extensive modifications to the Waste Gas Analyzer and Waste Gas System were performed requiring these systems be opened. Prior to closure, steps were performed to purge these systems with nitrogen *. However, the design of these systems does not lend itself to effective purging.
Furthermore, the calibration of the Waste Gas Analyzer introduced additional o 2 into the system. This was further complicate~ due to the fact that the online o 2 analyzer was out of service for replacement.
o 2 concentration within the Waste Gas System was reduced to < 2% on 12/12/93, at 0408 hours, at which time the TS Action Statement was exited. Lessons learned from this event will be incorporated into future planning regarding Waste Gas System modifications.
o 2 concentration within the Waste Gas System was reduced to < 2% on 12/12/93, at 0408 hours, at which time the TS Action Statement was exited. Lessons learned from this event will be incorporated into future planning regarding Waste Gas System modifications.
NRC Form 366 (6-891 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1. DOCKET NUMBER 5000272 PLANT AND SYSTEM IDENTIFICATION:
NRC Form 366 (6-891
Westinghouse  
 
-Pressurized Water Reactor LER NUMBER 93-019..:00 PAGE 2 of 4 Energy Industry Identification System (EIIS) codes are identified in the text as {xx} IDENTIFICATION OF OCCURRENCE:
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station       DOCKET NUMBER      LER NUMBER      PAGE Unit 1.                         5000272         93-019..:00    2 of 4 PLANT AND SYSTEM IDENTIFICATION:
Westinghouse   - Pressurized Water Reactor Energy Industry Identification System (EIIS) codes are identified in the text as {xx}
IDENTIFICATION OF OCCURRENCE:
Waste Gas Holdup System Oxygen Concentration Greater Than 2% For More Than 48 Hours
Waste Gas Holdup System Oxygen Concentration Greater Than 2% For More Than 48 Hours
* Event Date: 12/5/93 Report Date: 1/4/94 This report was initiated by Incident Report No. 93-494. CONDITIONS PRIOR TO OCCURRENCE:
* Event Date:   12/5/93 Report Date:   1/4/94 This report was initiated by Incident Report No. 93-494.
CONDITIONS PRIOR TO OCCURRENCE:
Mode 5; 11th refueling/maintenance outage in progress; Reactor core reload complete DESCRIPTION OF OCCURRENCE:
Mode 5; 11th refueling/maintenance outage in progress; Reactor core reload complete DESCRIPTION OF OCCURRENCE:
Oxygen concentration within the Waste Gas Holdup System {WE} was greater than 2% for more than 48 hours, which exceeded Technical Specification (TS) Action Statement 3.11.2.5.a.
Oxygen concentration within the Waste Gas Holdup System {WE} was greater than 2% for more than 48 hours, which exceeded Technical Specification (TS) Action Statement 3.11.2.5.a.
On December 3, 1993, at 0910 hours,' TS .Action Statement 3-.11.2.5.a.
On December 3, 1993, at 0910 hours,' TS .Action Statement 3-.11.2.5.a.
was entered due to oxygen concentration of 2.17% by volume as measured in 13 Waste* Gas Decay Tank (WGDT). Efforts to reduce the oxygen concentrat:ion to< 2% were implementtad.
was entered due to oxygen concentration of 2.17% by volume as measured in 13 Waste* Gas Decay Tank (WGDT). Efforts to reduce the oxygen concentrat:ion to< 2% were implementtad. oxygen concentrations above*
oxygen concentrations above* 2% were subsequently measured in other WGDTs; 3.04% in 11 WGDT on December 8, 3.11% in 14 WGDT on December 8, and 3.29% in 12 WGDT on December 9. The maximum measured concentration was 4.25% in 13 WGDT on December 4. Oxygen.concentration within the Waste Gas Holdup System was reduced to less than 2% on December 12, 1993 at 0408 hours, at which time the TS -Action Statement was exited. ANALYSIS OF OCCURRENCE:
2% were subsequently measured in other WGDTs; 3.04% in 11 WGDT on December 8, 3.11% in 14 WGDT on December 8, and 3.29% in 12 WGDT on December 9. The maximum measured concentration was 4.25% in 13 WGDT on December 4. Oxygen.concentration within the Waste Gas Holdup System was reduced to less than 2% on December 12, 1993 at 0408 hours, at which time the TS -Action Statement was exited.
There is an increased probability of oxygen concentration greater than 2% within the Waste Gas Holdup System after a refueling/maintenance outage. oxygen may enter the Waste Gas Holdup System via the eves Holdup Tanks, the Reactor Coolant Drain Tank, the Pressurizer Relief Tank, and the Volume Control Tank (VCT). The valves which provide direct flow to the Waste Gas Header when these tanks are opened to the LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating station Unit 1 DOCKET NUMBER 5000272 ANALYSIS OF OCCURRENCE: (cont'd) LER NUMBER 93-019-00 PAGE 3 of 4 ambient atmosphere are required to be closed. In addition, extensive modifications to the Waste Gas Analyzer and the Waste Gas System were performed.*
ANALYSIS OF OCCURRENCE:
There is an increased probability of oxygen concentration greater than 2% within the Waste Gas Holdup System after a refueling/maintenance outage. oxygen may enter the Waste Gas Holdup System via the eves Holdup Tanks, the Reactor Coolant Drain Tank, the Pressurizer Relief Tank, and the Volume Control Tank (VCT). The valves which provide direct flow to the Waste Gas Header when these tanks are opened to the
 
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating station       DOCKET NUMBER    LER NUMBER        PAGE Unit 1                           5000272         93-019-00        3 of 4 ANALYSIS OF OCCURRENCE: (cont'd) ambient atmosphere are required to be closed. In addition, extensive modifications to the Waste Gas Analyzer and the Waste Gas System were performed.*
APPARENT CAUSE OF OCCURRENCE:
APPARENT CAUSE OF OCCURRENCE:
The root cause is attributed to "Design, Manufacturing, Construction/Installation", as per NUREG-1022.
The root cause is attributed to "Design, Manufacturing, Construction/Installation", as per NUREG-1022. The source of the oxygen is attributed to routine refueling/ maintenance outage .
The source of the oxygen is attributed to routine refueling/
activities. In addition, extensive modifications to the Waste Gas Analyzer and Waste Gas System were* performed requiring th*ese systems be opened~ Prior to closure, steps were performed to purge the_se systems with nitrogen. However, the design of these systems does not lend itself to effective purging. Furthermore, the calibrat~on of the Waste Gas Analyzer introduced additional oxygen into the system. This situation was further complicated due to the fact that the online oxygen analyzer was out of service for replacement.
maintenance outage . activities.
In addition, extensive modifications to the Waste Gas Analyzer and Waste Gas System were* performed requiring th*ese systems be Prior to closure, steps were performed to purge the_se systems with nitrogen.
However, the design of these systems does not lend itself to effective purging. Furthermore, the of the Waste Gas Analyzer introduced additional oxygen into the system. This situation was further complicated due to the fact that the online oxygen analyzer was out of service for replacement.
PREVIOUS SIMILAR OCCURRENCES:
PREVIOUS SIMILAR OCCURRENCES:
LER 272/87-019-00 reported a similar event in the Waste Gas System. Corrective actions to the 1987 event have been effective for normal . refueling/maintenance outage activities.
LER 272/87-019-00 reported a similar event in the Waste Gas System.
SAFETY SIGNIFICANCE This event is reportable in accordance with lOCFR 50.73(a) (2) (i) (B), since TS Action statement 3.11.2.5.a was not met. This event did not affect the health or safety of the public. The concern for oxygen within the Waste Gas Holdup System is due to the presence of hydrogen gas within the system*. In sufficient quantities, hydrogen in the presence of oxygen can be explosive.
Corrective actions to the 1987 event have been effective for normal .
The TS level of not greater than 2% oxygen is conservatively low, ensuring that this explosive hazard is not present. Monitoring of the oxygen concentration in accordance with TS ensures that if the concentration increases above the 2% limitation, expeditious corrective action can* be taken to lower the level to below 2%. During this event the highest-measured hydrogen concentration was 1.51%, therefore potential for an explosive mixture of hydrogen and oxygen in the Waste Gas Holdup system did not exist. CORRECTIVE ACTION: oxygen concentration within the Waste Gas system was reduced to less than 2% on December 12, 1993 at 0408 hours, at.which time the TS Action Statement was exited.
refueling/maintenance outage activities.
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 CORRECTIVE ACTION: (cont'd) DOCKET NUMBER 5000272 LER NUMBER 93-019-00 PAGE 4 of 4 Lessons learned from this event will be incorporated into future planning regarding Waste Gas System MJPJ:pc SORC Mtg. 94-001 eneral Manager -Salem Operations}}
SAFETY SIGNIFICANCE This event is reportable in accordance with 10CFR 50.73(a) (2) (i) (B),
since TS Action statement 3.11.2.5.a was not met.
This event did not affect the health or safety of the public. The concern for oxygen within the Waste Gas Holdup System is due to the presence of hydrogen gas within the system*. In sufficient quantities, hydrogen in the presence of oxygen can be explosive. The TS level of not greater than 2% oxygen is conservatively low, ensuring that this explosive hazard is not present. Monitoring of the oxygen concentration in accordance with TS ensures that if the concentration increases above the 2% limitation, expeditious corrective action can*
be taken to lower the level to below 2%. During this event the highest-measured hydrogen concentration was 1.51%, therefore potential for an explosive mixture of hydrogen and oxygen in the Waste Gas Holdup system did not exist.
CORRECTIVE ACTION:
oxygen concentration within the Waste Gas system was reduced to less than 2% on December 12, 1993 at 0408 hours, at.which time the TS Action Statement was exited.
 
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station     DOCKET NUMBER     LER NUMBER     PAGE Unit 1                          5000272          93-019-00     4 of 4 CORRECTIVE ACTION:  (cont'd)
Lessons learned from this event will be incorporated into future planning regarding Waste Gas System modi:j:~
eneral Manager -
Salem Operations MJPJ:pc SORC Mtg. 94-001}}

Latest revision as of 10:21, 23 February 2020

LER 93-019-00:on 931203,TS Action Statement Entered Due to Waste Gas Holdup Sys Oxygen Concentration Being Greater than 2% for More than 48 H.Oxygen Concentration within Waste Gas Sys Reduced to Less than 2% on 931212.W/940104 Ltr
ML18100A835
Person / Time
Site: Salem PSEG icon.png
Issue date: 01/04/1994
From: Pastva M, Vondra C
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-93-019, LER-93-19, NUDOCS 9401310028
Download: ML18100A835 (5)
v • d • e


Text

.. . e PStiG

  • Public Service Electric arid Gas Company *P.O. Box 236

. Salem Generating Station January 4, 199'} t./

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*93-019-0b.

This Licensee Event Report is being submitted pursuant to the .

requirements of Code of Federal Regulation 10CFR50.73(a) (2) (i)(B).

This report is required to be issued within thirty (30) days of event discovery.

Sincerely yours, MJPJ:pc Distribution 9401310028 940104 ~*

PDR ADOCK 05000272 S PDR l i I

TherxJ'i\'cr is 11; your hands.

. 95*2189 REV 7-92

l NRC FORM-366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104 (6-891

. EXPIRES: 4/30/92

.ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD LICENSEE EVENT REPORT (LERI COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT- BRANCH (P-530). U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON. DC 20555. AND TO THE PAPERWORK REDUCTION PROJECT 13150-01041, OFFICE OF MANAGEMENT AND BUDGET. WASHINGTON, DC :20503.

FACILITY NAME (11 DOCKET NUMBER 121 I PAGE 131 Salem Generating Station-- Unit 1 TITLE (41 Io 15IoIoIo12 I 712 1 loF 0 14 Waste Gas Holdup System Oxygen Concentration Greater Than :z% For More Than 48 Hours.

EVENT DATE (51 LER NUMBER 161 REPORT DATE (71 OTHER FACILITIES INVOLVED (Bl MONTH DAY YEAR YEAR

\?? SEQUENTIAL NUMBER it\ REVlSION NUMBER MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERISI o1s1010101 I I ii 2 ol 5 9 3 913 - ol 1 19 - o lo 0I1 ol4 9[ 4 0 1 5 IO J.O I O I I I THIS REPORT IS SUBMITTED PURSUANT TO THE R~OUIREMENTS OF 10 CFR §: (Ch*_ck ono or moro of th* fo/low;ngJ 1111 OPERATING MODE (91 5 20.402(bl 20.405lcl ,_ 60.73l*ll2Hivl ,___ 73.71lbl 20.405(o)(1llil 50.36(cll1l 60.73_(*11211*1 73.71 lcl 0 0 2~.40511)(1)(iil 50.36lcll21

,___ 60.7311l121(vii) OTHER !Specify in Absrrocl

.-.- - x btJ/ow tJnd in T1Jxt, NRC Form

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,,,. 20.4051o)(1 lliiil 20.40511)(1 )(iv)*

-,___ 50.731*ll2llil 50.7311)(2)(iil 50.7311H2llviiil!AI 60.7311l12)(viiillBl

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LICENSEE CONTACT FOR THIS LER (121 NAME TELEPHONE NUMBER AREA CODE M. J. Pastva, Jr. - LER.Coordinator COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN *THIS REPORT 1131 CAUSE SYSTEM COMPONENT M~~~~~C- R~6°~~:g;E i:::: "\:  :::::,:Y::?:F CAUSE SYSTEM COMPONENT

'MANUFAC-TURER I I I I I I I *:*: I I I I I I I

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}: :}:-:-:::::;:;::;::-:* -:-:-:*:*

I I I I I I I I I I I I I I SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY YEAR EXPECTED

~NO SUBMISSION DATE 1151

~YES (If v*s. comp/*<* EXPECTED SUBMISSION DATE!

I I I ABSTRACT (Umii to 1400 spaces, i.ll., approximately fifrsen single-space rvpewrirren lines) (16) oxygen (0 2 ) concentration within the waste Gas Holdup System was > 2%

for > 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. On 12/3/93, at 0910 hours0.0105 days <br />0.253 hours <br />0.0015 weeks <br />3.46255e-4 months <br />, Technical Specification (TS)

Action Statement 3.11.2.5.a. was entered due to o 2 concentration of

  • 2.17% by volume in 13 Waste Gas Decay Tank (WGDT). Efforts to reduce the o~ concentration to < 2% were implemented ..- o 2 concentrations above 2~ were subsequently measured in other WGDTs; 3.04% in 11 WGDT on 12/8/93, .3.11% in 14 WGDT on 12/8/93, and 3.29% in 12 WGDT on 12/9/93.

_The maximum o 2 concentration was 4.25% in 13 WGDT on 12/4/93. The root cause is attributed to "Design, Manufacturing, Construction/

Installation", as per NUREG-1022. The source of the o is attributed to routine refueling/ maintenance outage activities~ fn addition, extensive modifications to the Waste Gas Analyzer and Waste Gas System were performed requiring these systems be opened. Prior to closure, steps were performed to purge these systems with nitrogen *. However, the design of these systems does not lend itself to effective purging.

Furthermore, the calibration of the Waste Gas Analyzer introduced additional o 2 into the system. This was further complicate~ due to the fact that the online o 2 analyzer was out of service for replacement.

o 2 concentration within the Waste Gas System was reduced to < 2% on 12/12/93, at 0408 hours0.00472 days <br />0.113 hours <br />6.746032e-4 weeks <br />1.55244e-4 months <br />, at which time the TS Action Statement was exited. Lessons learned from this event will be incorporated into future planning regarding Waste Gas System modifications.

NRC Form 366 (6-891

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1. 5000272 93-019..:00 2 of 4 PLANT AND SYSTEM IDENTIFICATION:

Westinghouse - Pressurized Water Reactor Energy Industry Identification System (EIIS) codes are identified in the text as {xx}

IDENTIFICATION OF OCCURRENCE:

Waste Gas Holdup System Oxygen Concentration Greater Than 2% For More Than 48 Hours

  • Event Date: 12/5/93 Report Date: 1/4/94 This report was initiated by Incident Report No.93-494.

CONDITIONS PRIOR TO OCCURRENCE:

Mode 5; 11th refueling/maintenance outage in progress; Reactor core reload complete DESCRIPTION OF OCCURRENCE:

Oxygen concentration within the Waste Gas Holdup System {WE} was greater than 2% for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, which exceeded Technical Specification (TS) Action Statement 3.11.2.5.a.

On December 3, 1993, at 0910 hours0.0105 days <br />0.253 hours <br />0.0015 weeks <br />3.46255e-4 months <br />,' TS .Action Statement 3-.11.2.5.a.

was entered due to oxygen concentration of 2.17% by volume as measured in 13 Waste* Gas Decay Tank (WGDT). Efforts to reduce the oxygen concentrat:ion to< 2% were implementtad. oxygen concentrations above*

2% were subsequently measured in other WGDTs; 3.04% in 11 WGDT on December 8, 3.11% in 14 WGDT on December 8, and 3.29% in 12 WGDT on December 9. The maximum measured concentration was 4.25% in 13 WGDT on December 4. Oxygen.concentration within the Waste Gas Holdup System was reduced to less than 2% on December 12, 1993 at 0408 hours0.00472 days <br />0.113 hours <br />6.746032e-4 weeks <br />1.55244e-4 months <br />, at which time the TS -Action Statement was exited.

ANALYSIS OF OCCURRENCE:

There is an increased probability of oxygen concentration greater than 2% within the Waste Gas Holdup System after a refueling/maintenance outage. oxygen may enter the Waste Gas Holdup System via the eves Holdup Tanks, the Reactor Coolant Drain Tank, the Pressurizer Relief Tank, and the Volume Control Tank (VCT). The valves which provide direct flow to the Waste Gas Header when these tanks are opened to the

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 93-019-00 3 of 4 ANALYSIS OF OCCURRENCE: (cont'd) ambient atmosphere are required to be closed. In addition, extensive modifications to the Waste Gas Analyzer and the Waste Gas System were performed.*

APPARENT CAUSE OF OCCURRENCE:

The root cause is attributed to "Design, Manufacturing, Construction/Installation", as per NUREG-1022. The source of the oxygen is attributed to routine refueling/ maintenance outage .

activities. In addition, extensive modifications to the Waste Gas Analyzer and Waste Gas System were* performed requiring th*ese systems be opened~ Prior to closure, steps were performed to purge the_se systems with nitrogen. However, the design of these systems does not lend itself to effective purging. Furthermore, the calibrat~on of the Waste Gas Analyzer introduced additional oxygen into the system. This situation was further complicated due to the fact that the online oxygen analyzer was out of service for replacement.

PREVIOUS SIMILAR OCCURRENCES:

LER 272/87-019-00 reported a similar event in the Waste Gas System.

Corrective actions to the 1987 event have been effective for normal .

refueling/maintenance outage activities.

SAFETY SIGNIFICANCE This event is reportable in accordance with 10CFR 50.73(a) (2) (i) (B),

since TS Action statement 3.11.2.5.a was not met.

This event did not affect the health or safety of the public. The concern for oxygen within the Waste Gas Holdup System is due to the presence of hydrogen gas within the system*. In sufficient quantities, hydrogen in the presence of oxygen can be explosive. The TS level of not greater than 2% oxygen is conservatively low, ensuring that this explosive hazard is not present. Monitoring of the oxygen concentration in accordance with TS ensures that if the concentration increases above the 2% limitation, expeditious corrective action can*

be taken to lower the level to below 2%. During this event the highest-measured hydrogen concentration was 1.51%, therefore potential for an explosive mixture of hydrogen and oxygen in the Waste Gas Holdup system did not exist.

CORRECTIVE ACTION:

oxygen concentration within the Waste Gas system was reduced to less than 2% on December 12, 1993 at 0408 hours0.00472 days <br />0.113 hours <br />6.746032e-4 weeks <br />1.55244e-4 months <br />, at.which time the TS Action Statement was exited.

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 93-019-00 4 of 4 CORRECTIVE ACTION: (cont'd)

Lessons learned from this event will be incorporated into future planning regarding Waste Gas System modi:j:~

eneral Manager -

Salem Operations MJPJ:pc SORC Mtg.94-001

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