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| issue date = 08/29/1985
| issue date = 08/29/1985
| title = Responds to NRC 850730 Ltr Re Violations Noted in Insp Repts 50-272/85-01 & 50-311/85-04.Corrective Actions:Surveillance Procedures SP(O)4.4.6.2 & SP(O)4.4.6.2d & Operating Instruction II-1.3.5 Re RCS Coolant Revised
| title = Responds to NRC 850730 Ltr Re Violations Noted in Insp Repts 50-272/85-01 & 50-311/85-04.Corrective Actions:Surveillance Procedures SP(O)4.4.6.2 & SP(O)4.4.6.2d & Operating Instruction II-1.3.5 Re RCS Coolant Revised
| author name = MCNEILL C A
| author name = Mcneill C
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| addressee name = EBNETER S D
| addressee name = Ebneter S
| addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
| addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
| docket = 05000272, 05000311
| docket = 05000272, 05000311
Line 14: Line 14:
| page count = 3
| page count = 3
}}
}}
See also: [[followed by::IR 05000272/1985001]]


=Text=
=Text=
{{#Wiki_filter:* Public Service Electric and Gas Company Corbin A. McNeill, Jr. Vice President  
{{#Wiki_filter:*
-Public Service Electric and Gas Company P.O. Box236, Hancocks Bridge, NJ 08038 609 339-4800 Nuclear * August 29, 1985 U.S. Nuclear Regulatory  
Corbin A. McNeill, Jr.
Commission  
Vice President -
Region I 631 Park Avenue King of Prussia, PA 19406 Attention:  
Nuclear Public Service Electric and Gas Company Public Service Electric and Gas Company P.O. Box236, Hancocks Bridge, NJ 08038 609 339-4800 August 29, 1985 U.S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 Attention:   Stewart D. Ebneter, Director Division of Reactor Safety Gentlemen:
Stewart D. Ebneter, Director Division of Reactor Safety Gentlemen:  
NRC INSPECTION 50-272~1 AND 50-311/85-04 SALEM GENERATING STAT~
NRC INSPECTION  
UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 Public Service Electric and Gas Company is in receipt of your letter dated July 30, 1985 which transmitted a Notice of Violation concerning a failure to establish adequate procedures.
AND 50-311/85-04  
Pursuant to the provisions of 10 CFR 2.201, our response to the Notice of Violation is provided in Attachment 1.
SALEM GENERATING  
Sincerely, Attachment C Mr. Donald c. Fischer Licehsing Project Manager Mr. Thomas J. Kenny Senior Resident Inspector
UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 Public Service Electric and Gas Company is in receipt of your letter dated July 30, 1985 which transmitted  
* eso9100114 e~g~~72
a Notice of Violation  
          ~DR ADOCK 0       PDR
concerning  
 
a failure to establish  
r.
adequate procedures.  
ATTACHMENT 1 10CFR PART 2.201 INFORMATION PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM GENERATING STATION RESPONSE TO NOTICE OF VIOLATION Your letter dated July 30, 1985 identified a violation of Technical Specification 6.8 which requires that written procedures be established and maintained. Contrary to this requirement, Surveillance Procedure (SP) 4.4.6.2d, RCS Water Inventory Balance, was inadequately established in that:   (1) leakage occurring outside containment (i.e., intersystem leakage) was not classified as either identified or unidentified leakage in accordance with Regulatory Guide 1.45; (2) no correction was made to account for temperature changes during the test; (3) use of inappropriate identified leakage values into the Reactor Coolant Drain Tank (RCDT) and; (4) either computer or manual calculations could be used to generate the test results, allowing selection of the more favorable result and frequent use of the less precise manual calculation.
Pursuant to the provisions  
: 1. PSE&G DOES NOT DISPUTE THE VIOLATION *
of 10 CFR 2.201, our response to the Notice of Violation  
* 2.
is provided in Attachment  
3.
1. Attachment  
THE ROOT CAUSE OF THE PROBLEM WAS A FAILURE OF OPERATIONS DEPARTMENT SUPERVISORY PERSONNEL TO RECOGNIZE THAT THIS ACTIVITY WAS BEING CONDUCTED IN A NON-CONSERVATIVE MANNER.
C Mr. Donald c. Fischer Licehsing  
IMMEDIATE CORRECTIVE ACTION:
Project Manager Mr. Thomas J. Kenny Senior Resident Inspector  
Surveillance Procedures SP(0)4.4.6.2, SP(0)4.4.6.2d, and Operating Instruction II-1.3.5 have been revised, where appropriate, to require the following:
eso9100114 ADOCK 0 PDR Sincerely, 
        - Entry into the appropriate Technical Specification action statement prior to attempting to differentiate between unidentified leakage and non-Reactor Coolant System leakage.
r. * * * ATTACHMENT  
        - Reactor Coolant System (RCS) temperature (Tave) shall be the same at the beginning and end of the test.
1 lOCFR PART 2.201 INFORMATION  
        - Reactor Coolant Drain Tank level input shall be taken during the test interval.
PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM GENERATING  
        - The P250 computer, test 39, shall be the primary method of performing the leak rate calculation when the RCS is at or greater than 547°F and 2235 psig *
STATION RESPONSE TO NOTICE OF VIOLATION  
 
Your letter dated July 30, 1985 identified  
          "I:
a violation  
        ~
of Technical  
: 4. LONG TERM CORRECTIVE ACTIONS PSE&G continues to stress the importance of accountability to all levels of employees. Where appropriate, corrective actions will not only include those personnel directly involved in questionable activities but also the responsible supervisory personnel.
Specification  
: 5. WE ARE NOW IN FULL COMPLIANCE *
6.8 which requires that written procedures  
be established  
and maintained.  
Contrary to this requirement, Surveillance  
Procedure (SP) 4.4.6.2d, RCS Water Inventory  
Balance, was inadequately  
established  
in that: (1) leakage occurring  
outside containment (i.e., intersystem  
leakage) was not classified  
as either identified  
or unidentified  
leakage in accordance  
with Regulatory  
Guide 1.45; (2) no correction  
was made to account for temperature  
changes during the test; (3) use of inappropriate  
identified  
leakage values into the Reactor Coolant Drain Tank (RCDT) and; (4) either computer or manual calculations  
could be used to generate the test results, allowing selection  
of the more favorable  
result and frequent use of the less precise manual calculation.  
1. PSE&G DOES NOT DISPUTE THE VIOLATION  
* 2. THE ROOT CAUSE OF THE PROBLEM WAS A FAILURE OF OPERATIONS  
DEPARTMENT  
SUPERVISORY  
PERSONNEL  
TO RECOGNIZE  
THAT THIS ACTIVITY WAS BEING CONDUCTED  
IN A NON-CONSERVATIVE  
MANNER. 3. IMMEDIATE  
CORRECTIVE  
ACTION: Surveillance  
Procedures  
SP(0)4.4.6.2, SP(0)4.4.6.2d, and Operating  
Instruction  
II-1.3.5 have been revised, where appropriate, to require the following:  
-Entry into the appropriate  
Technical  
Specification  
action statement  
prior to attempting  
to differentiate  
between unidentified  
leakage and non-Reactor  
Coolant System leakage. -Reactor Coolant System (RCS) temperature (Tave) shall be the same at the beginning  
and end of the test. -Reactor Coolant Drain Tank level input shall be taken during the test interval.  
-The P250 computer, test 39, shall be the primary method of performing  
the leak rate calculation  
when the RCS is at or greater than 547°F and 2235 psig *
_,, "! .:. * * * "I: "' 4. LONG TERM CORRECTIVE  
ACTIONS PSE&G continues  
to stress the importance  
of accountability  
to all levels of employees.  
Where appropriate, corrective  
actions will not only include those personnel  
directly involved in questionable  
activities  
but also the responsible  
supervisory  
personnel.  
5. WE ARE NOW IN FULL COMPLIANCE  
* ac2 3-4
* ac2 3-4
}}
  *}}

Latest revision as of 08:11, 3 February 2020

Responds to NRC 850730 Ltr Re Violations Noted in Insp Repts 50-272/85-01 & 50-311/85-04.Corrective Actions:Surveillance Procedures SP(O)4.4.6.2 & SP(O)4.4.6.2d & Operating Instruction II-1.3.5 Re RCS Coolant Revised
ML18092A765
Person / Time
Site: Salem  PSEG icon.png
Issue date: 08/29/1985
From: Corbin McNeil
Public Service Enterprise Group
To: Ebneter S
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8509100114
Download: ML18092A765 (3)
v • d • e


Text

Corbin A. McNeill, Jr.

Vice President -

Nuclear Public Service Electric and Gas Company Public Service Electric and Gas Company P.O. Box236, Hancocks Bridge, NJ 08038 609 339-4800 August 29, 1985 U.S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 Attention: Stewart D. Ebneter, Director Division of Reactor Safety Gentlemen:

NRC INSPECTION 50-272~1 AND 50-311/85-04 SALEM GENERATING STAT~

UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 Public Service Electric and Gas Company is in receipt of your letter dated July 30, 1985 which transmitted a Notice of Violation concerning a failure to establish adequate procedures.

Pursuant to the provisions of 10 CFR 2.201, our response to the Notice of Violation is provided in Attachment 1.

Sincerely, Attachment C Mr. Donald c. Fischer Licehsing Project Manager Mr. Thomas J. Kenny Senior Resident Inspector

  • eso9100114 e~g~~72

~DR ADOCK 0 PDR

r.

ATTACHMENT 1 10CFR PART 2.201 INFORMATION PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM GENERATING STATION RESPONSE TO NOTICE OF VIOLATION Your letter dated July 30, 1985 identified a violation of Technical Specification 6.8 which requires that written procedures be established and maintained. Contrary to this requirement, Surveillance Procedure (SP) 4.4.6.2d, RCS Water Inventory Balance, was inadequately established in that: (1) leakage occurring outside containment (i.e., intersystem leakage) was not classified as either identified or unidentified leakage in accordance with Regulatory Guide 1.45; (2) no correction was made to account for temperature changes during the test; (3) use of inappropriate identified leakage values into the Reactor Coolant Drain Tank (RCDT) and; (4) either computer or manual calculations could be used to generate the test results, allowing selection of the more favorable result and frequent use of the less precise manual calculation.

1. PSE&G DOES NOT DISPUTE THE VIOLATION *
  • 2.

3.

THE ROOT CAUSE OF THE PROBLEM WAS A FAILURE OF OPERATIONS DEPARTMENT SUPERVISORY PERSONNEL TO RECOGNIZE THAT THIS ACTIVITY WAS BEING CONDUCTED IN A NON-CONSERVATIVE MANNER.

IMMEDIATE CORRECTIVE ACTION:

Surveillance Procedures SP(0)4.4.6.2, SP(0)4.4.6.2d, and Operating Instruction II-1.3.5 have been revised, where appropriate, to require the following:

- Entry into the appropriate Technical Specification action statement prior to attempting to differentiate between unidentified leakage and non-Reactor Coolant System leakage.

- Reactor Coolant System (RCS) temperature (Tave) shall be the same at the beginning and end of the test.

- Reactor Coolant Drain Tank level input shall be taken during the test interval.

- The P250 computer, test 39, shall be the primary method of performing the leak rate calculation when the RCS is at or greater than 547°F and 2235 psig *

"I:

~

4. LONG TERM CORRECTIVE ACTIONS PSE&G continues to stress the importance of accountability to all levels of employees. Where appropriate, corrective actions will not only include those personnel directly involved in questionable activities but also the responsible supervisory personnel.
5. WE ARE NOW IN FULL COMPLIANCE *
  • ac2 3-4
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