ML20141K517
| ML20141K517 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/16/1997 |
| From: | Jaudon J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Richard Anderson FLORIDA POWER CORP. |
| References | |
| 50-302-96-19, EA-96-365, EA-96-465, EA-96-527, NUDOCS 9705290190 | |
| Download: ML20141K517 (5) | |
See also: IR 05000302/1996019
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May 16,1997
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EA 96-365
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EA 96-465
EA 96-527
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'tlorida Power Corporation.
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Crystal River Energy Complex
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Mr. Roy A. Anderson (SA2A)
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Sr. VP. Nuclear Operations
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ATTN:
Mgr.. Nuclear Licensing
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15760 West Power Line. Street
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Crystal River. FL 34428-6708
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SUBJECT:
NOTICE OF VIOLATION (NRC INSPECTION REPORT NO. 50-302/96-19)
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Dear Mr. Anderson:
Thank you for your response of April 11. 1997, to our Notice of Violation
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(NOV) issued on March 12, 1997, concerning activities conducted at your
Crystal River facility. We have evaluated your response and found that it
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does not meet all of the requirements of 10 CFR 2.201. Although your response
addrc sed the overall root cause for the significant decrease in performance.
your response did not completely address'the s)ecific corrective actions for
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each of the individual violations, and, as sucl. failed to address all of the
corrective actions to prevent recurrence and the expected completion dates.
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Our specific concerns are provided in the enclosure and were discussed
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generally between Mssrs. J. Holden. R. Grazio, and D. Kunsemiller of your
staff and Mssrs. R. Schin. S. Cahill, and K. Landis of the NRC staff on May 7.
Therefore. we request that you provide a supplemental response to the Notice
within 30 days from the date of this letter to include a description of any
action you have taken or plan to take and the expected completion dates to
improve performance in the engineering area at Crystal River.
Sincerely.
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Orig signed by Johns P. Jaudon
Johns P. Jaudon. Director
Division of Reactor Safety
Enclosure: Additional Supplemental
Response Issues
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Docket No. 50-302
License No. DPR-72
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0FFICIAL COPY
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9705290190 970516
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ADOCK 05000302
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cc w/ encl: John P.. Cowan. Vice President
Nuclear Production (SA2C)
FPC, Crystal River Energy Complex
15760 West Power Line Street
Crystal River. FL 34428-6708
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B. J. Hickle. Director
Nuclear Plant Operations (NA2C)
FPC Crystal River Energy Complex
15760 West Power Line Street .
Crystal River. FL 34428-6708
David F. Kunsemiller. Director (SA2A)
Nuclear Operations Site Support
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FPC. Crystal River Energy Complex
15760 West Power Line Street
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Crystal River. FL 34428-6708
R. Alexander Glenn. Corporate Counsel
Florida Power Corporation
MAC - ASA
P. O. Box 14042
St. Petersburg FL 33733-4042
Attorney General
Department of Legal Affairs
The Capitol
Tallahassee, FL 32304
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Bill Passetti
Office of Radiation Control
De3artment of Health and
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Rehabilitative Services
1317 Winewood Boulevard
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Tallahassee, FL 32399-0700
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Joe Myers. Director
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Div. of Emergency Preparedness
Department of Community Affairs
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2740 Centerview Drive
Tallahassee. FL 32399-2100
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Chairman
Board of County Commissioners
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Citrus County
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110 N. Apopka Avenue
Inverness. FL 34450-4245
Robert B. Borsum
Framatome Technologies
1700 Rockville Pike. Suite 525
Rockville. MD 20852-1631
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Distribution w/ encl:
L. Raghavan. NRR
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C. Crowley. RII
G. Hopper. RII
PUBLIC
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NRC Resident Inspector
- U.S. Nuclear Regulatory Comm.
6745 N. Tallahassee Road
Crystal River. FL 34428
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Areas needing a supplemental response in addition to the Florida Power
Corporation letter of April 11, 1997, responding to NRC NOV of March 12. 1997:
1.
Details were missing for some of the corrective actions:
a.
For Violation A.2: action 5) on page 7 stated that design basis
training, including design assumptions on equipment availability
and limitations, will be provided to targeted personnel. This
violation involved an emergency operating procedure (EOP) change
that inappropriately increased emergency diesel generator (EDG)
loading without that fact being addressed in the EDG loading
analysis.
The corrective action did not identify who the targeted
personnel will be - will they be all of the personnel who will be
doing the E0P change reviews?
b.
For Violation A.2.: action d) on page 7 stated that the emergency
operating procedures are being revised as part of the E0P
Enhancement Program.
The revised procedures will have appropriate
reviews by design personnel and will be issued prior to restart
from the present outage. The corrective action did not state, for
future E0P changes that are not part of the E0P Enhancement
Program, what action will be taken to prevent recurrence of the
violation.
c.
For Violation A.3 - This violation involved an operating procedure
change that inappropriately increased EDG loading without that
fact being addressed in the EDG loadirig analysis.
The corrective
actions as stated did not address how the review of operating
procedure changes will be improved to prevent recurrence of this
violation.
d.
Action 3 on page 13 stated: "To resolve example 4. FPC will
address Nuclear Engineering Procedure guidance and design control
issues under Restart Issue OP-6.~
The specific corrective
actions, including extent of condition and completion dates, were
not included in your letter.
e.
The " Additional information regarding these violations" on page 15
stated: "The issues identified by these violations are being
addressed through the CR-3 corrective action program which
includes the extent of conditions review program." This implies
that there are other significant specific corrective actions to be
taken that are not included in your letter.
2.
Completion dates were not given for several of the corrective actions
that will be taken:
a.
No completion date was given for Violation A.2 action a) on page
7: The FSAR. Enhanced Design Basis Document, and Analysis Basis
Document will be updated to show EDG and EFW equipment
dependencies and equipment limitations.
Enclosure
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b.
No completion date was given for Violation A.2 action b) on page
7: Design basis training, including design assumptions on
equipment availability and limitations, will be provided to
targeted personnel.
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c.
No completion date was given for Violation A.3. action on page 7:
FPC will amend the ITS BASES and update the CR-3 FSAR to' include
MUP-1B as being a selectable Engineered Safeguards load.
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d.
No completion date was given for action 4.c on pcge 13: A new
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series of drawings to clearly identify the penetration
configurations is being developed.
3.
The corrective actions did not ideatify plant modifications to be
accomplished as corrective actions for each violation.
For example:
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The corrective actions for Violation A.4.. on page 7. did not
include the installation of an emergency teedwater flow limiti.ng
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ventJri modification.
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b.
The corrective actions for Violation A.5, on page 7, did not
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iaclude the installation of an ASV-204 mcdification.
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Enclosure