ML20154N446
| ML20154N446 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 05/24/1988 |
| From: | Miraglia F Office of Nuclear Reactor Regulation |
| To: | Mulley G NRC OFFICE OF INSPECTOR & AUDITOR (OIA) |
| References | |
| NUDOCS 8806020304 | |
| Download: ML20154N446 (6) | |
Text
.__
May 24,1988.
MEMORANDUM FOR:
George A. Mulley, Jr.
Assistant' Director for Investigations M4M Office of Inspector and Auditor
'FROM:
. Frank J. Miraglia Associate Director for Projects i
Office of Nuclear Reactor Regulation
SUBJECT:
STATUS OF TECHNICAL ISSUES PROVIDED TO OIA DURING THE FORT ST. VRAIN NUCLEAR GENERATING STATION INVESTIGATION
Reference:
April 29, 1987 memo from S.R. Connelly, 01A to V. Stello, Jr., ED0 on this subject The memorandum provides an update of the technical status of these issues where relevant. This update was requested orally by S. Goldberg, OIA in discussions with K. Heitner, NRR, on May 4, 1988.
Building 10 - NRR completed two Safety Evaluations (SEs) on Building 10. The electrical modification SE was dated January 25, 1988 and the structural SE was dated March 10, 1988. This review is completed and no safety issues remain.
PCRV Tendon Corrosion - The staff is considering two actions on this issue.
The first would relax the current six month surveillance interval to one year. The second would request the licensee to provide an evaluation of the PCRV design margins now and at end of life based on observed tendon conditions.
At this time, the condition of the tendons does not affect the safety of the plant.
Control Rod Drive Mechanisms (CRDMs) - The staff has allowed the licensee more time to gain cperating experience before a new surveillance program is developed.
No CRDM failures or abnormal behavior have been reported, thus, there are no new safety issues arising from the CRDMs.
Equi ament Qualification (EQ) - There has not been any further NRR involvement in tiis issue. However, in completing the EQ progren, the staff conducted a team inspection at the site and found no major problems.
Please contact K. Heitner, NRR, Project Manager for Fort St. Vrain at X21333 if there are any questions.
c+isim2 a te.ned by 8806020304 880524 IrNk'JINaNia gDR ADOCK0500g7 Associate Director for Projects Office of Nuclear Reactor Regulation cc:
See next page DISTRIBUTION,,
. Docket; F,ile m NRC PDR Local PDR PD4 Reading
.L. Rubenstein J. Calvo P. Noonan K. Heitner 0GC-Rockville E. Jordan J. Partlow ACRS(10)
PD4 Plant File F. Miraglia D. Cru?.chfield T. Rehm, EDO T. Murley, NRR T. Westerman, RIV J. Callan, RIV R. Martin, RIV
- See previous concurrences:
PD4/LA*
PD4/PM*
PD4/D*
DR4A*
PNoonan KHeitner:sr JCalvo LRubenstein 05/16/88 05/13/88 05/17/88 05/18/88 DRSP:D*
A DCrutchfield F
ia 05/18/88 05
MEMORANDUM FORT George ' A'. Mulley, Jr.
, Assistant Director for Investigations Office of Inspector and Auditor FROM:
Frank J. Miraglia Associate Director for. Projects.
Office of Nuclear Reactor Regulation
SUBJECT:
STATUS OF TECHNICAL ISSUES PROVIDED TO
'l OIA DURING THE FORT ST. VRAIN NUCLEAR GENERATING STATION INVESTIGATION
Reference:
April 29, 1987 memo from S.R. Connelly,
.01A to V. Stello, Jr., ED0 on this subject The' memorandum provides an update of the technical status of these issues where relevant. This update was requested orally by S. Goldberg, OIA in discussions with K. Heitner, NRR,on May 4, 1988.
Building 10 - NRR completed two Safety Evaluations (SEs) on Building 10. The electrical modification SE was dated January 25, 1983 and the structural SE was dated March 10, 1988. This review is completed and no safety issues remain.
PCRV Tendon Corrosion - The staff is considering two actions on this issue.
The first would relax the-current six month surveillance interval to one year. The second would request the licensee to provide an evaluation of the PCRV design margins now and at end of life based on observed tendon conditions.
At this time, the condition of the tendons does not affect the safety of the pl ant.
Control Rod Drive Mechanisms (CRDMs) - The staff has allowed the licensee more time to gain operating experience before a new surveillance program is developed..
No CRDM failures or abnormal behavior have been reported, thus, there are no new safety issues arising from the CRDMs.
Equi 3 ment Qualification (EQ)_ - There has not been any further NRR involvement in t11s issue. However, in completing the EQ program, the staff conducted a team inspection at the site and found no major problems.
Please contact K. Heitner, NRR, Project Manager for Fort St. Vrain at X21333 if there are any questions.
Frank J. Miraglia Associate Director for Projects Office of Nuclear Reactor Regulation cc: See next page DISTRIBUTION Docket File NRC PDR Local PDR PD4 Reading L. Rubenstein J. Calvo P. Noonan K. Heftner OGC-Rockville E. Jordan J. Partlow ACRS(10)
PD4 Plant File F. Miraglia D. Crutchfield
- See prev.ious concurrence:
/g PD4/L M PD4/PM*
PD4/D/Nc DR4A %
PNoonM/
KHeitner:sr JCalvo LRubenstein 05//(0/88 05/13/88 05//7/88 05/6/88 DR ADP DC ed FMiraglia 05//j(/88 05/ /88
tiEVORANDUM FOR:
George A. Mulley, Jr.
Assistant Director for Investigations Office of The Inspector and Auditor FROM:
Frank J. Miraglia Associate Director for Projects Office-of Nuclear Reactor Regulation
SUBJECT:
STATUS OF TECHNICAL ISSUES PROVIDED T0 01A DURING THE FORT ST. VRAIN NUCLEAR GENERATING STATION INVESTIGATION
Reference:
April 29, 1987 memo.from S.R. Connelly, 01A to V. Stello, Jr., ED0 on this subject.
The memorandum provides an update of the technical status of these issues where relevant. This update was requested orally by S. Goldberg, 0IA in discussions with K. Heitner, NRR on May 4, 1988.
Building 10 - Nr1R completed two Safety Evaluations (SEs) on Building 10. The electrical modification SE was dated January 25, 1988 and the structural SE was dated March 10, 1988. This review is completed and no safety issues remain.
PCRV Te_ndon Corrosion - The staff is considering two actions on this issue.
The first would relax the current six month surveillance interval to one year. The second would request the licensee to provide an evaluation of the PCRV design margins now and at end of life based on observed tendon conditions.
At this time, the condition of the tendons does not affect the safety of the plant.
Control Rod Drive Mechanisms - The staff has allowed the licensee more time to gain operating experience before a new surveillance program is developed.
No CRDM failures or abnormal behavior have been reported, thus, there are no new safety issues arising from the CRDMs.
j Equipment Qualification - There has not been any further NRR involvement in l
this iss'oe. However, in ccmpleting the EQ program, the staff conducted a team inspection at the site and found no major problems.
Please contact K. Heitner, NRR, Project Manager for Fort St. Vrain at X21333 if there are any questions.
Frank J. Miraglia, Associate Director for Projects Office of Nuclear Reactor Regulation cc: See next page DISTRIBUTION Docket File NRC PDR Local PDR PD4 Reading L. Rubenstein J. Calvo P. Noonan K. Heitner OGC-Rockville E. Jordan J. Partlow ACRS (10)
PD4 Plant File F. Miraglia D. Crutchfield N
PD4/D DR4A PD4/LA PD4/PM PNoonan KHeitner:sr JCalvo LRubenstein 05/ /88 05/L3/88 05/ /88 05/ /88 DRSP:D ADP DCrutchfield FMiraglia 05/ /88 05/ /88
May 24,1988 MEMORANDUM FOR:
George A. Mulley, Jr.
Assistant Director for Investigations A-Office of Inspector and Auditor FROM:
Frank J. Miraglia Associate Director for Projects Office of Nuclear Reactor Regulation
SUBJECT:
STATUS OF TECHNICAL ISSUES PROVIDED TO OIA DURING THE FORT ST. VPAIN NUCLEAR GENERATING STATION INVESTIGATION
Reference:
April 29, 1987 memo from S.R. Connelly.
OIA to V. Stello, Jr., ED0 on this subject The memorandum provides an update of the technical status of these issues where relevant. This update was requested orally by S. Goldberg, OIA in discussions with K. Heitner, NRR, on May 4, 1988.
Building 10 - NRR completed two Safety Evaluations (SEs) on Building 10. The electrical modification SE was dated January 25, 1988 and the structural SE was dated March 10, 1988. This review is completed and no safety issues remain.
PCRV Tendon Corrosion - The staff is considering two. actions on this issue.
The first would relax the current six month surveillance interval to one year. The second would regt est the licensee to provide an evaluation of the PCRV design margins new and at end of life based on observed tendon conditions.
At this time, the condition of the tendons does not affect the safety of the plant.
Control Rod Drive Mechanisms (CRCMs) - The staff has allowed the licensee more time to gain operating experience before a new surveillance program is developed.
No CRDM failures or abnormal behavior have been reported, thus, there are no new safety issues arising from the CRDMs.
I Equi ament Qualification (EQ) - There has not been any further NRR involvement in t11s issue. However, in completing the EQ program, the staff conducted a team inspection at the site and found no major problems.
l Please contact K. Heitner, NRR, Project Manager for Fort St. Vrain at X21333 l
if there are any questions.
orig 1%ytm n k J N a*giia Associate Director for Projects Office of Nuclear Reactor Regulation cc: See next page DISTRIBUTION Docket File.
NRC PDR Local PDR PD4 Reading L. Rubenstein J. Calvo P. Noonan K. Heitner OGC-Rockville E. Jordan J. Partlow ACRS(10)
PD4 Plant File F. Miraglia D. Crutchfield T. Rehm, EDO T. Murley, NRR T. Wcsterman, RIV J. Callan, RIV R. Martin, RIV
- See previous concurrences:
PD4/LA*
PD4/PM*
PD4/D*
DR4A*
PNoonan KHeitner:sr JCalvo LRubenstein 05/16/88 05/13/88 05/17/88 05/18/88 DRSP:D*
AD DCrutchfield F
'a 05/18/88 05
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UNITED STATES g
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NUCLEAR REGULATORY COMMISSION
- j WASHING TON. D. C. 20555 g,l. v,/
May 24,1988 MEMORANDUM FOR:
George A. Mulley, Jr.
Assistant Director for Investigations Office of Inspector and Auditor FROM:
Frank J. Miraglia Associate Director for Projects Office of Nuclear Reactor Regulation
SUBJECT:
STATUS OF TECHNICAL ISSUES PROVIDED TO OIA DURING THE FORT ST. VRAIN NUCLEAR GENERATING STATION INVESTIGATION
Reference:
April 29, 1987 memo from S.R. Connelly, OIA to V. Stello, Jr., ED0 on this subject The memorandum provides an update of the techaical status of these issues where relevant. This update was requested orally '>y S. Goldberg, 0IA in discussions with K. Heitner, NRR, on May 4, 1988.
Building 10 - NRR completed two Safety Evaluations (SEs) on Building 10.
The electrical modification SE was dated January 25, 1988 and the structural SE was dated March 10, 1988. This review is completed and no safety issues remain.
PCRV Tendon Corrosion - The staff is considering two actions on this issue.
The first would relax the currert six month surveillance interval to one year.
The second would request the licensee to provide an evaluation of the PCRV design margins now and at end of life based on observed tendon conditions.
At this time, the condition of the tendons does not affect the safety of the plant.
Control Rod Drive Mechanisms (CRDMs) - The staff has allowed the licensee more time to gain operating experience before a new surveillance program is developed.
No CRDM failures or abnormal behavior nave been reported, thus, there are no new safety issues arising from the CRDMs.
Equi rent Qualification (EQ) - There has not been any further NRR involvement in tiis issue. However, in completing the EQ program, the staff conducted a team inspection at the site and found no major problems.
l Please contact K. Heitner, NRR, Project Manager for Fort St. Vrain at X21333 if there are any questions.
h 4(_
Frank [MirgYfa Associate Director for Projects Office of Nuclear Reactor Regulation cc:
See next page
4 g.. cc:
S. Connelly, OIA S. Goldberg, DIA V. St'ello, E00 T. Murley, NRR l