ML19343A419: Difference between revisions
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| contact person = | | contact person = | ||
| document report number = 80-50-01X-0, 80-50-1X, NUDOCS 8009170381 | | document report number = 80-50-01X-0, 80-50-1X, NUDOCS 8009170381 | ||
| document type = REPORTABLE OCCURRENCE REPORT (SEE ALSO AO | | document type = REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER), TEXT-SAFETY REPORT | ||
| page count = 2 | | page count = 2 | ||
}} | }} | ||
=Text= | =Text= | ||
{{#Wiki_filter:, | {{#Wiki_filter:, | ||
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BOSTON EDISCN CCMPANT D | |||
Date/Ti:ne: Sept. 11, 198p 1200 Telephone Number Ta: Director, Region I. | ua TELECOPY MESSAGE Ta: | ||
Assigned Lt.~.4 Number 80-050/01I-0 Even: | 15-337-5324 Date/Ti:ne: Sept. 11, 198p 1200 Telephone Number Ta: Director, Region I. | ||
From: Pilgrim Nuclear Power Station Office of Inspectica and Enforcement RFD #1 Rocky Hill Road U. S. Nuclear Regulatory Commission Ply =outh, MA 02360 631 Park Avenue King of Prussia, PA 19406 Subj ect: | |||
?ROMPT REPORTA3LE OCCURRENCE Docke: Number 50-293; License DPR-35 Assigned Lt.~.4 Number 80-050/01I-0 Even: | |||
== Description:== | == Description:== | ||
Licensee Event Report 80-050/01X-0 is being submitted in accordance with the requirements of PNPS Technical Specification 6.9.3.1.b. | Licensee Event Report 80-050/01X-0 is being submitted in accordance with the requirements of PNPS Technical Specification 6.9.3.1.b. | ||
I Cause and Corrective Action: Root cause of this occurrence is sparse and anbiguous technical | Management review of station operating conditiens concluded that a plant shutdown was not commenced as required by Technical Specification. | ||
I Cause and Corrective Action: Root cause of this occurrence is sparse and anbiguous technical spscifications for operation with installed alternate shutdown panels. | |||
Fccility Status: | Fccility Status: | ||
* Ther:nal MW c) Routine Starm.tp | 100 | ||
g) Shutdown d) Routine Shuticwn | * Ther:nal MW c) Routine Starm.tp | ||
NRC person notified | ~ | ||
eN Mail- (2) copies to-Director. ' | g) Shutdown d) Routine Shuticwn h) Refueling c) Steady' State x | ||
l, | 'i) Other f) Load' Changing j) Not Applicaple A wri::en follow-up report v4'? be sent within two weeks. | ||
NRC person notified Mr. K. Roberts Prep'ared by Mr. M. T. Mhoughlin 8 o 0 917 0 3iil eN Mail- (2) copies to-Director. ' | |||
Washi=gton, D.C.- 20535 | l, Office of Management Information and ?rogram Control U. S. Nuclear Regula:ory Co-unission. | ||
Washi=gton, D.C.- | |||
20535 | |||
BOS' N EDISON COMPANY | BOS' N EDISON COMPANY 6 | ||
s PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 Attachment to LER 80-050/01X-0 Description On September. 10, 1980 at approximately 1700 hours a management review concluded that a Technical Specification violation had occurred. The violation occurred on. September.7, 1980. | |||
On September 7,- 1980 whila performing surveillance tests prior to removing ' A' diesel generator from service it was determined that RBCCW pump 'P202D was inoperable.- Although RBCCW pump P202D was inoperable, the Watch Engineer per-mitted the diesel generator to be. removed. from service at that time because it | On September 7,- 1980 whila performing surveillance tests prior to removing ' A' diesel generator from service it was determined that RBCCW pump 'P202D was inoperable.- Although RBCCW pump P202D was inoperable, the Watch Engineer per-mitted the diesel generator to be. removed. from service at that time because it was known that there were installed spares in each of the RBCCW loops. | ||
was known that there were installed spares in each of the RBCCW loops. | However, the September 10,.1980 management review concluded that since alternate shutdown panels installed during the last refueling outage restricted remote control of.the RBCCW pumps-to two of three installed units per loop and since RBCCW pump P202D was one of those two,. thac 'A' diesel generator should not have been removed from service. | ||
However, the September 10,.1980 management review concluded that since alternate shutdown panels installed during the last refueling outage restricted remote control of.the RBCCW pumps- to two of three installed units per loop and since RBCCW pump P202D was one of those two,. thac 'A' diesel generator should not have been removed from service | Cause & Corrective Action 1 | ||
Cause & Corrective Action | The sparse and ambiguous language of the Technical Specifications is believed to be the rope cause of this occurrence.in that the Limiting Condition for Operation of the Safe Shutdown Panels is not clearly defined. | ||
Upon identification of this situation a reactor shutdown was immediately initiated but terminated at approximately 1810 hours on September 10, 1980, following the return of the ' A' diesel generator to service. Additionally, a priority ' A' maintenance request was issued to return RBCCW pump P202D to operable status. | |||
Upon identification of this situation a reactor shutdown was immediately | To provide long term corrective action it is contemplated that following ad-d1tional review of the existing equipment and their requirements that two action items will be proposed.. | ||
initiated but terminated at approximately 1810 hours on September 10, 1980, following the return of the ' A' diesel generator to service. Additionally, a priority ' A' maintenance request was issued to return RBCCW pump P202D to operable status. | 1 A design change to plant equipment and, 2_ Technical Specification revision to clarify the LCO's for operation with installed alternate shutdown panels. | ||
To provide long term corrective action it is contemplated that following ad-d1tional review of the existing equipment and their requirements that two action items will be proposed. . | i l | ||
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Latest revision as of 16:11, 24 December 2024
| ML19343A419 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 09/11/1980 |
| From: | Mcloughlin M BOSTON EDISON CO. |
| To: | |
| References | |
| 80-50-01X-0, 80-50-1X, NUDOCS 8009170381 | |
| Download: ML19343A419 (2) | |
Text
,
r i
BOSTON EDISCN CCMPANT D
ua TELECOPY MESSAGE Ta:
15-337-5324 Date/Ti:ne: Sept. 11, 198p 1200 Telephone Number Ta: Director, Region I.
From: Pilgrim Nuclear Power Station Office of Inspectica and Enforcement RFD #1 Rocky Hill Road U. S. Nuclear Regulatory Commission Ply =outh, MA 02360 631 Park Avenue King of Prussia, PA 19406 Subj ect:
?ROMPT REPORTA3LE OCCURRENCE Docke: Number 50-293; License DPR-35 Assigned Lt.~.4 Number 80-050/01I-0 Even:
Description:
Licensee Event Report 80-050/01X-0 is being submitted in accordance with the requirements of PNPS Technical Specification 6.9.3.1.b.
Management review of station operating conditiens concluded that a plant shutdown was not commenced as required by Technical Specification.
I Cause and Corrective Action: Root cause of this occurrence is sparse and anbiguous technical spscifications for operation with installed alternate shutdown panels.
Fccility Status:
100
- Ther:nal MW c) Routine Starm.tp
~
g) Shutdown d) Routine Shuticwn h) Refueling c) Steady' State x
'i) Other f) Load' Changing j) Not Applicaple A wri::en follow-up report v4'? be sent within two weeks.
NRC person notified Mr. K. Roberts Prep'ared by Mr. M. T. Mhoughlin 8 o 0 917 0 3iil eN Mail- (2) copies to-Director. '
l, Office of Management Information and ?rogram Control U. S. Nuclear Regula:ory Co-unission.
Washi=gton, D.C.-
20535
BOS' N EDISON COMPANY 6
s PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 Attachment to LER 80-050/01X-0 Description On September. 10, 1980 at approximately 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> a management review concluded that a Technical Specification violation had occurred. The violation occurred on. September.7, 1980.
On September 7,- 1980 whila performing surveillance tests prior to removing ' A' diesel generator from service it was determined that RBCCW pump 'P202D was inoperable.- Although RBCCW pump P202D was inoperable, the Watch Engineer per-mitted the diesel generator to be. removed. from service at that time because it was known that there were installed spares in each of the RBCCW loops.
However, the September 10,.1980 management review concluded that since alternate shutdown panels installed during the last refueling outage restricted remote control of.the RBCCW pumps-to two of three installed units per loop and since RBCCW pump P202D was one of those two,. thac 'A' diesel generator should not have been removed from service.
Cause & Corrective Action 1
The sparse and ambiguous language of the Technical Specifications is believed to be the rope cause of this occurrence.in that the Limiting Condition for Operation of the Safe Shutdown Panels is not clearly defined.
Upon identification of this situation a reactor shutdown was immediately initiated but terminated at approximately 1810 hours0.0209 days <br />0.503 hours <br />0.00299 weeks <br />6.88705e-4 months <br /> on September 10, 1980, following the return of the ' A' diesel generator to service. Additionally, a priority ' A' maintenance request was issued to return RBCCW pump P202D to operable status.
To provide long term corrective action it is contemplated that following ad-d1tional review of the existing equipment and their requirements that two action items will be proposed..
1 A design change to plant equipment and, 2_ Technical Specification revision to clarify the LCO's for operation with installed alternate shutdown panels.
i l
4