ML17334B762
| ML17334B762 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/07/1998 |
| From: | Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Fitzpatrick E AMERICAN ELECTRIC POWER CO., INC. |
| Shared Package | |
| ML17334B763 | List: |
| References | |
| 50-315-98-04, 50-315-98-4, 50-316-98-04, 50-316-98-4, CAL-3-97-011, CAL-3-97-11, EA-98-150, EA-98-151, EA-98-152, EA-98-186, NUDOCS 9805180108 | |
| Download: ML17334B762 (12) | |
See also: IR 05000315/1998004
Text
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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9805180108
DOC.DATE: 98/05/07
NOTARIZED: NO
DOCKET
ACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana
M
05000315
50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana
M
05000316
AUTH.NAME
AUTHOR AFFILIATION
GROBE,J.A.
Region
3
(Post
820201)
RECIP.NAME
RECIPIENT AFFILIATION
FITZPATRICK,E.
American .Electric Power Co., Inc.
SUBJECT:
Forwards insp'repts
50-315/98-04
Ec 50-316/98-04
S CAL-3-97-
011 on 980109-27.No violations noted.Insp validated
'orrective
actions initiated to address
significant safety
issues
revealed
through
NRC AE'nsp in Aug
Ec Sept
1997.
DISTRIBUTION CODE: IEOIF
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SIZE: 5 +
TITLE: General
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May 7,
1998
EAs98-150, 98-151,98-152, 98-186
Mr. E. E. Fitzpatrick
Executive Vice President
Nuclear Generation Group
American Electric Power Company
500 Circle Drive
Buchanan, Ml 49107-1395
'UBJECT:
INSPECTION REPORT NO. 50-315/98004(DRS); 50-316/98004(DRS) AND
CONFIRMATORYACTION LETTER (CAL) NO. RIII-97-011 VALIDATION
Dear Mr. Fitzpatrick:
On January 27, 1998, the NRC completed an inspection at your D. C. Cook, Units 1 and 2
reactor facility. The purpose of the inspection was to validate the corrective actions you
initiated to address significant safety issues revealed through the NRC Architect/Engineer (AE)
insp'ection conducted in August and September 1997. Those corrective actions are
documented
in Confirmatory Action Letter (CAL) No. Rill-97-011. We determined that you
made satisfactory progress on the CAL commitments, but also identified a number of apparent
violations of NRC regulations.
The results of the inspection are documented in the enclosed
report.
The corrective action commitments documented in the CAL included actions to address specific
AE inspection issues and the completion of a short term assessment
to provide reasonable
assurance
that similar issues did not adversely impact the operability of other safety systems
at the Cook nuclear facility. While a number of items willcontinue to be reviewed by our staff,
the results of our inspection indicate that you have made satisfactory progress in completing the
actions specified in the CAL. Specifically, our inspection confirmed: the completion of physical
modifications to the Unit 1 and Unit 2 recirculation sumps and compressed
air systems; the
completion of calculations and analyses that demonstrate the capability to safely shutdown and
cooldown the plant in the event of a design basis accident; the revision of emergency and
operating procedures to address single failure criteria and other concerns; the submittal of
Technical Specification amendment requests to your facilitylicenses; the conduct of training for
your staff; and the adequate completion of a short term assessment
to bound the impact of the
engineering deficiencies on equipment operability. We discussed your actions taken in
response to the CAL during a number of public meetings conducted in late 1997 through
January 1998.
In the long term, your corrective action plans include implementation of an expanded instrument
uncertainty program, which is scheduled to be completed by the end of 1998.
Further, the
inspectors considered your staffs efforts good in identifying other avenues that could bypass
the design control process.
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During review of engineering activities to asses the adequacy of your response to the CAL
issues, twelve apparent violations were identified that could be considered for escalated
enforcement action in accordance with the "General Statement of Policy and Procedure for
NRC Enforcement Actions" (Enforcement Policy), NUREG-1600.
Three apparent violations of 10 CFR 50.59(b)(1) were identified concerning the failure to
perform a safety evaluation for proposed changes to the plant design basis.
These apparent
violations resulted from your staff's failure to recognize that the implemented changes
constituted a change to the plant's design basis.
Additionally, seven apparent violations of 10 CFR 50.59(b)(1) were identified pertaining to inadequate safety evaluations.
This issue is of
particular concern as two of the deficient evaluations had recently been reviewed as part of
your self-assessment
and found acceptable by your staff.
One apparent violation of 10 CFR 50 Appendix B, Criterion III, "Design Control," was identified
pertaining to the failure to assure that the containment spray heat exchanger room heat gain
calculation incorporated design input values that were consistent with the UFSAR. This was of
concern because the nonconservative input values used allowed temperatures
to exceed
design for the containment spray heat exchanger room under accident conditions.
'ne
apparent violation of 10 CFR Appendix B, Criterion XVI,"Corrective Action," was identified
concerning the failure to implement effective corrective actions.
Specifically, corrective actions
taken for previous occurrences
did not prevent the installation of leak collection devices prior to
performing an engineering review.
In addition, our inspection identified weaknesses
in your
quality assurance
(QA) organization audit methodology which contributed to your inability to
self-identify AE inspection findings.
No Notice of Violation is presently being issued for these apparent violations. The actions
necessary to correct the above apparent violations would be similar to planned or completed
actions that you willdiscuss during the predecisional enforcement conference currently
scheduled for May 20, 1998. Therefore, you willbe advised by separate correspondence
of the
results of our deliberations on this matter.
No response regarding these apparent violations is
required at this time.
In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and its
enclosure will be placed in the NRC Public Document Room.
~l
E. Fitzpatrick
l
We willgladly discuss any questions you have concerning this inspection.
Sincerely,
original /s/ by J. A. Grobe
John A. Grobe, Director
Division of Reactor Safety
Docket Nos:
50-315; 50-316
License Nos:
Enclosure:
Inspection Report Nos. 50-315/98004(DRS);
50-316/98004(DRS)
cc w/encl:
John Sampson,
Site Vice
President
A. A. Blind, Vice President
Nuclear Engineering
Douglas Cooper, Plant Manager
Richard Whale, Michigan Public
Service Commission
Michigan Department of
Environmental Quality
Emergency Management
Division, Ml Department
of State Police
DocuMENT NAME: G:)DRS<DCC98004.DRS
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DATE
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We willgladly discuss any questions you have concerning this inspection.
Sincerely,
John A. Grobe, Director
Division of Reactor Safety
Docket Nos.:
50-315; 50-316
License Nos.:
cc w/encl:
John Sampson, Site Vice
President
A. A. Blind, Vice President
Nuclear Engineering
Douglas Cooper, Plant Manager
Richard Whale, Michigan Public
Service Commission
Michigan Department of
Environmental Quality
Emergency Management
Division, Ml Department
of State Police
Dis~tr'tio:
Project Mgr., NRR w/encl
A. Beach w/encl
J. Caldwell w/encl
B. Clayton w/encl
DRP w/encl
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PUBL'IC IE-01 w/encl
Docket File w/encl
GREENS
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DOCDESK (E-Mail)
DOCUMENT NAME: G:iDRSttDCC98004.DRS
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