ML19347B688
| ML19347B688 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 10/01/1980 |
| From: | Robert Lewis NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Ferguson J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| Shared Package | |
| ML19347B690 | List: |
| References | |
| NUDOCS 8010150550 | |
| Download: ML19347B688 (1) | |
See also: IR 05000338/1980029
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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REGION 11
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101 MARIETT A ST., N.W., SUITE 3100
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ATLANTA, G EoRGI A 30303
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OCT 0 i 1980
In Reply Refer To:
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50-339/80-28-}
U-338/80-29
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Virginia Electric & Power Company
ATTN:
J. H. Ferguson, Executive
Vice President-Power
P. O. Box 26666
Richmond, VA 23261
1
Gentlemen:
Thank you for your letter of September 12, 1980, informing us of steps you have
taken to correct the items of noncompliance concerning activities under NRC
Operating License Nos. NPF-4 and NPF-7 brought to your attention in our letter
of August 20, 1980. We will examine your corrective actions and plans during
subsequent inspections.
We appreciate your cooperation with us.
Sincerely,
[ich6.
R
. Lewis, Acting Chief
Reactor Operations & Nuclear
Support Branch
cc:
W. R. Cartwright, Station Manager
P. G. Perry, Senior Resident
Engineer
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VIRGINIA ELucTHIC AND l'OWEH CObt PA NY /
H renwonn,VImora zA 20261
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September 12, 1980
Mr. James P. O'Reilly, Director
Serial No. 738
Office of Inspection and Enforcement
N0/RMT:ms
U. S. Nuclear Regulatory Commission
Docket Nos. 50-338
Region II
50-339
101 Marietta Street, Suite 3100
License Nos. NPF-4
Atlanta, Georgia
30303
hTF-7
Dear Mr. O'Reilly:
We have reviewed your letter of August 20, 1980 in reference to the inspection
conducted at North Anna Power Station on June 2 through July 11, 1980, and
reported in IE Inspection Report Nos. 50-338/80-29 and 50-339/80-28.
Our
responses to the specific infractions are attached.
We have determined that no proprietary information is contained in the
reports.
Accordingly, the Virginia Electric and Power Company has no objec-
tion to these inspection reports being made a matter of public disclosure.
Very truly yours,
9fdbeL
B. R. Sylvia
Manager - Nuclear
Operations and Maintenance
Attachment
cc:
Mr. Robert A. Clark, Chief
Operating Reactors Branch N-
3
Division of Licensing
Mr. B. Joe Youngblood
Licensing Branch No. 1
Division of Licensing
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Attachment
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RESPONSE TO NOTICE OF VIOLATION
ITEtt REPORTED DURING NRC-INSPECTION
CONDUCTED FROM JUNE 2, THROUGH JULY 11, 1980
NRC C0}DIENT
A.
License No. NPF-4 Technical Specification 3.3.1.1 Table 3.3-1 for Steam
Generator Water Level Low-Low and Low Steam Generator Water Level Note 7
requires that if the number of operable channels is one less than the
total number of channels, startup and power operations may proceed until
the next required Channel Functional Test provided the inoperable channel
is placed in the tripped condition within one hour.
Contrary to the above, on June 12, 1980, while operating in Mode I the
inoperable Steam Generator I uvel channel was not placed in the tripped
condition within one hour.
'
This is an infraction.
RESPONSE
The above infraction is correct as stated.
Specifically, pursuant to
Section 2.201 of the NRC's " Rules of Practice", Part 2, Title 10, Code
of Federal Regulations, the following information is submitted:
1.
Corrective steps taken and results achieved:
When indication for
LT-1474 began to deviate from the other two channels, Operations
personnel questioned the operability of the channel.
The instru-
ment shop was notified and the calibration of the channel was
checked.
It was noted that the control room indication fluctuated
over time and periodically returned to within the tolerances speci-
fied on 1-LOG-4.
A containment entry was made and it was discovered
that there was 'a steam leak on the upper transmitter isolation root
valve.
Based on these actions to determine the operability of the
channel, the channel was placed in trip when it was determined by
the Operations Superintendent that the channel was,
in fact,
2.
Corrective action taken to avoid further non-compliance:
Standing
Order No. I was changed to give specific instructions to the control
room operators concerning the criteria to use in determining when to
place a channel in'the tripped condition.
In the future, when the
readings noted on the control room logs do not meet the specified
acceptance tolerances, the actions specified in the appropriate Tech
Spec will be taken immediately. Any related investigation to deter-
mine the status of the subject channel will be performed subsequent
to placing the channel in trip.
3.
Date when full compliance will be achieved:
Full
compliance was
achieved by September 10, 1980.
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AttaclhEent
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Page 3
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RESPONSE TO NOTICE OF VIOLATION
ITEM REPORTED DURING NRC INSPECTION
CONDUCTED FROM JUNE 2 THROUGH JULY 11, 1980
NRC COMMENT
C.
License No. NPF-7 Technical Specification 3.3.1.1 Table 3.3-1 for Steam / -
Feedwater Flow Mismatch Note 7 requires that if the number of operable
channels is one less than the total number of channels, startup and power
l
operations may proceed until the next required Channel Functional Test,
provided the inoperable channel is placed in the tripped condition within
one hour. - Additionally, Technical Specification 3.0.3 states that is a
,
Limiting Condition for Operation and/or associated action requirements
{
cannot be satisfied because of circumstances in excess of those addressed
in the specification, the unit shall be placed in at least Hot Standby
within one hour and Hot Shutdown within the next six hours.
Contrary to the requirements aoove, on June 19, 1980, while in operating
Mode 2,
the inoperable Feedwater Flow Channels were not placed in the
tripped condition within one hour nor was the unit placed in Hot Standby
within one hour or Hot Shutdown within the next six hours.
This is an infraction.
RESPONSE
The above infraction is correct as stated.
Specifically, pursuant to
Section 2.201 of the NRC's " Rules of Practice", Part 2, Title 10, Code of
Federal Regulations, the following information is submitted:
1.
Corrective steps taken and results achieved:
Vepco operating
personnel received reinstruction via a standing order revision rela-
ted to placing inoperable instrumentation in a tripped condition.
2.
Corrective action taken to avoid further non-compliance:
Reinstruc-
tion
should
enhance
more
expeditious
handling of
instrument channels.
3.
Date when full compliance will be achieved:
Full
compliance was
achieved by September 10, 1980.
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