ML18153C287: Difference between revisions

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See also: [[followed by::IR 05000280/1990018]]


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{{#Wiki_filter:* ~~-----VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 July 11, 1990 United States Nuclear Regulatory  
{{#Wiki_filter:* ~~-----VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 July 11, 1990 United States Nuclear Regulatory Commission Attention:
Commission  
Document Control Desk Washington, D. C. 20555 Gentlemen:
Attention:  
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 REPLY TO A NOTICE OF VIOLATION Serial No. NURPC Docket Nos. -License Nos. 90-349 R2 50-280 50-281 DPR-32 DPR-37 NRC INSPECTION REPORT NOS. 50-280/90-18 AND 50-281/90-18 Pursuant to the provisions of 1 O CFR 2.201, we have reviewed your letter dated May 30, 1990, in reference to the NRC inspection conducted on April 16 -20, 1990, for Surry Power Station. _ The inspection was reported in Inspection Report Nos. 50-280/90-18 and 50-281/90-18.
Document Control Desk Washington, D. C. 20555 Gentlemen:  
Our response to the violation described in the Notice of Violation is provided in Attachment
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 REPLY TO A NOTICE OF VIOLATION  
: t. We have no objection to this inspection report being made a matter of public disclosure.
Serial No. NURPC Docket Nos. -License Nos. 90-349 R2 50-280 50-281 DPR-32 DPR-37 NRC INSPECTION  
REPORT NOS. 50-280/90-18  
AND 50-281/90-18  
Pursuant to the provisions  
of 1 O CFR 2.201, we have reviewed your letter dated May 30, 1990, in reference  
to the NRC inspection  
conducted  
on April 16 -20, 1990, for Surry Power Station. _ The inspection  
was reported in Inspection  
Report Nos. 50-280/90-18  
and 50-281/90-18.  
Our response to the violation  
described  
in the Notice of Violation  
is provided in Attachment  
t. We have no objection  
to this inspection  
report being made a matter of public disclosure.  
Should you have any further. questions, please contact us. Very truly yours, \SJ:t_~ W. L. Stewart Senior Vice President  
Should you have any further. questions, please contact us. Very truly yours, \SJ:t_~ W. L. Stewart Senior Vice President  
-Nuclear Attachment  
-Nuclear Attachment cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W. Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station 9007170104 900711 PDR ADOCK n~nno2so Q ----PDC
cc: U. S. Nuclear Regulatory  
* ATTACHMENT 1 REPL V TO A NOTICE OF VIOLATION REPORTED DURING THE NRC INSPECTIONS ON APRIL 16 -20, 1990 . INSPECTION REPORT NOS. 50-280/90-18 AND 50-281/90-18 NRC Comment During the Nuclear Regulatory Commission (NRC) inspection conducted on April 16 -20, 1990, a violation of NRC requirements was identified.
Commission  
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 1 O CFR Part 2, Appendix C (1990), the violation is listed below: 1 O CFR 20.103(b)(1) requires the licensee, as a precautionary procedure,use process or other engineering controls, to the extent practical, to limit concentrations of radioactive materials in air to levels below those which delimit an airborne radioactivity area as defined in 1 O CFR 20.203(d)(1  
Region II 101 Marietta Street, N. W. Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector  
Surry Power Station 9007170104  
900711 PDR ADOCK n~nno2so Q ----PDC
* ATTACHMENT  
1 REPL V TO A NOTICE OF VIOLATION  
REPORTED DURING THE NRC INSPECTIONS  
ON APRIL 16 -20, 1990 . INSPECTION  
REPORT NOS. 50-280/90-18  
AND 50-281/90-18  
NRC Comment During the Nuclear Regulatory  
Commission (NRC) inspection  
conducted  
on April 16 -20, 1990, a violation  
of NRC requirements  
was identified.  
In accordance  
with the "General Statement  
of Policy and Procedure  
for NRC Enforcement  
Actions," 1 O CFR Part 2, Appendix C (1990), the violation  
is listed below: 1 O CFR 20.103(b)(1)  
requires the licensee, as a precautionary  
procedure,use  
process or other engineering  
controls, to the extent practical, to limit concentrations  
of radioactive  
materials  
in air to levels below those which delimit an airborne radioactivity  
area as defined in 1 O CFR 20.203(d)(1  
)(ii) . 1 O CFR 20.203(d)(1  
)(ii) . 1 O CFR 20.203(d)(1  
)(ii) defines an airborne radioactivity  
)(ii) defines an airborne radioactivity area as any room, . enclosure, or operating area in which airborne radioactive materials composed wholly or partly of licensed material exist in concentrations which, averaged over the number of hours in any week during which individuals are in the area, exceed 25 percent of the amounts specified in Appendix B, Table I, Column 1 of Part 20. Contrary to the requirements specified above, the. licensee failed to utilize, process or other engineering controls to the extent practical to limit airborne radioactivity material below 25 percent (1 O MPC-Hrs/Wk) of the amounts specified in Appendix B, Table I, Column 1, in that, between March 23-30, 1990, licensee personnel were in an average airborne concentration of 25 Hrs/Wk when the radioactivity concentration in the licensee's Auxiliary Building reached 99 times that specified in Appendix B, Table I, Column 1, of Part 20, on March 26, 1990. This is a severity level IV violation (Supplement IV).
area as any room, . enclosure, or operating  
* RESPONSE TO NOTICE OF VIOLATION INSPECTION REPORT NOS. 50-280/90-18 AND 50-281/90-18 (1) ADMISSION OR DENIAL OF THE ALLEGED VIOLATION:
area in which airborne radioactive  
The violation is correct as stated. (2) REASONS FOR VIOLATION:
materials  
For a period of time prior to the loss of contamination control cited in this violation, a rubber hose had been in use to provide the dewatering flow path from the spent resin shipping containers in the Decontamination Building to a floor drain located in a high radiation area of the Auxiliary Building.
composed wholly or partly of licensed material exist in concentrations  
In addition, a contamination control barrier had been erected isolating this high radiation area of the Auxiliary Building.
which, averaged over the number of hours in any week during which individuals  
As reported to the NRC inspector and documented in the Notice of Violation, on or about March 23, 1990, the floor drain backed up and drained leaving residual contamination which was the source of the airborne contamination detected in the Auxiliary Building on March 26, 1990. During the time of the loss of contamination control, several ventilation flow perturbations occurred in the area. Contributing to these perturbations were balance problems associated with the Auxiliary Building's ventilation system, the sealing of several ventilation flow paths in adjacent areas, and the running of a Fuel Building heating supply fan without operating the associated area . exhaust fans. When the High Radiation Area door was opened for personnel access, radioactive contamination in the higher pressure area was transported into the previously clean area. (3) CORRECTIVE STEPS WHICH HAVE BEEN TAKEN AND RESULTS ACHIEVED:
are in the area, exceed 25 percent of the amounts specified  
: a. A permanent drain line has been installed and is in use for resin shipping container dewatering activities.
in Appendix B, Table I, Column 1 of Part 20. Contrary to the requirements  
: b. A matrix which describes proper ventilation alignment for different plant conditions has been prepared and provided to operating personnel for their use. ' c. The Auxiliary Building central and general ventilation exhaust systems have been balanced.
specified  
: d. Station operating procedures have been changed to require that a temporary modification (TM) be performed and documented for the use of temporary hookups which will be used for handling radioactive process fluids. Such TMs are reviewed by Radiological Engineering and approved by SNSOC prior to initial use .   
above, the. licensee failed to utilize, process or other engineering  
* (4) CORRECTIVE STEPS WHICH WILL BE TAKEN TO AVOID FURTHER VIOLATIONS:
controls to the extent practical  
Additional walkdowns will be conducted to determine if other contamination control barriers exist which could, under certain ventilation configurations, permit a similar event to take place. Any such installations will be evaluated and modified as necessary.
to limit airborne radioactivity  
(5) THE DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED:
material below 25 percent (1 O MPC-Hrs/Wk)  
System walkdowns will be completed and corrective actions will be implemented by September 30, 1990 .}}
of the amounts specified  
in Appendix B, Table I, Column 1, in that, between March 23-30, 1990, licensee personnel  
were in an average airborne concentration  
of 25 Hrs/Wk when the radioactivity  
concentration  
in the licensee's  
Auxiliary  
Building reached 99 times that specified  
in Appendix B, Table I, Column 1, of Part 20, on March 26, 1990. This is a severity level IV violation (Supplement  
IV).
* RESPONSE TO NOTICE OF VIOLATION  
INSPECTION  
REPORT NOS. 50-280/90-18  
AND 50-281/90-18  
(1) ADMISSION  
OR DENIAL OF THE ALLEGED VIOLATION:  
The violation  
is correct as stated. (2) REASONS FOR VIOLATION:  
For a period of time prior to the loss of contamination  
control cited in this violation, a rubber hose had been in use to provide the dewatering  
flow path from the spent resin shipping containers  
in the Decontamination  
Building to a floor drain located in a high radiation  
area of the Auxiliary  
Building.  
In addition, a contamination  
control barrier had been erected isolating  
this high radiation  
area of the Auxiliary  
Building.  
As reported to the NRC inspector  
and documented  
in the Notice of Violation, on or about March 23, 1990, the floor drain backed up and drained leaving residual contamination  
which was the source of the airborne contamination  
detected in the Auxiliary  
Building on March 26, 1990. During the time of the loss of contamination  
control, several ventilation  
flow perturbations  
occurred in the area. Contributing  
to these perturbations  
were balance problems associated  
with the Auxiliary  
Building's  
ventilation  
system, the sealing of several ventilation  
flow paths in adjacent areas, and the running of a Fuel Building heating supply fan without operating  
the associated  
area . exhaust fans. When the High Radiation  
Area door was opened for personnel  
access, radioactive  
contamination  
in the higher pressure area was transported  
into the previously  
clean area. (3) CORRECTIVE  
STEPS WHICH HAVE BEEN TAKEN AND RESULTS ACHIEVED:  
a. A permanent  
drain line has been installed  
and is in use for resin shipping container  
dewatering  
activities.  
b. A matrix which describes  
proper ventilation  
alignment  
for different  
plant conditions  
has been prepared and provided to operating  
personnel  
for their use. ' c. The Auxiliary  
Building central and general ventilation  
exhaust systems have been balanced.  
d. Station operating  
procedures  
have been changed to require that a temporary  
modification (TM) be performed  
and documented  
for the use of temporary  
hookups which will be used for handling radioactive  
process fluids. Such TMs are reviewed by Radiological  
Engineering  
and approved by SNSOC prior to initial use .   
* (4) CORRECTIVE  
STEPS WHICH WILL BE TAKEN TO AVOID FURTHER VIOLATIONS:  
Additional  
walkdowns  
will be conducted  
to determine  
if other contamination  
control barriers exist which could, under certain ventilation  
configurations, permit a similar event to take place. Any such installations  
will be evaluated  
and modified as necessary.  
(5) THE DATE WHEN FULL COMPLIANCE  
WILL BE ACHIEVED:  
System walkdowns  
will be completed  
and corrective  
actions will be implemented  
by September  
30, 1990 .
}}

Revision as of 14:50, 31 July 2019

Responds to Violations Noted in Insp Repts 50-280/90-18 & 50-281/90-18.Corrective Actions:Permanent Drain Line Installed & Matrix Which Describes Proper Ventilation Alignment for Plant Conditions Provided for Personnel Use
ML18153C287
Person / Time
Site: Surry  Dominion icon.png
Issue date: 07/11/1990
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
90-349, NUDOCS 9007170104
Download: ML18153C287 (4)
v • d • e


Text

  • ~~-----VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 July 11, 1990 United States Nuclear Regulatory Commission Attention:

Document Control Desk Washington, D. C. 20555 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 REPLY TO A NOTICE OF VIOLATION Serial No. NURPC Docket Nos. -License Nos.90-349 R2 50-280 50-281 DPR-32 DPR-37 NRC INSPECTION REPORT NOS. 50-280/90-18 AND 50-281/90-18 Pursuant to the provisions of 1 O CFR 2.201, we have reviewed your letter dated May 30, 1990, in reference to the NRC inspection conducted on April 16 -20, 1990, for Surry Power Station. _ The inspection was reported in Inspection Report Nos. 50-280/90-18 and 50-281/90-18.

Our response to the violation described in the Notice of Violation is provided in Attachment

t. We have no objection to this inspection report being made a matter of public disclosure.

Should you have any further. questions, please contact us. Very truly yours, \SJ:t_~ W. L. Stewart Senior Vice President

-Nuclear Attachment cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W. Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station 9007170104 900711 PDR ADOCK n~nno2so Q ----PDC

  • ATTACHMENT 1 REPL V TO A NOTICE OF VIOLATION REPORTED DURING THE NRC INSPECTIONS ON APRIL 16 -20, 1990 . INSPECTION REPORT NOS. 50-280/90-18 AND 50-281/90-18 NRC Comment During the Nuclear Regulatory Commission (NRC) inspection conducted on April 16 -20, 1990, a violation of NRC requirements was identified.

In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 1 O CFR Part 2, Appendix C (1990), the violation is listed below: 1 O CFR 20.103(b)(1) requires the licensee, as a precautionary procedure,use process or other engineering controls, to the extent practical, to limit concentrations of radioactive materials in air to levels below those which delimit an airborne radioactivity area as defined in 1 O CFR 20.203(d)(1

)(ii) . 1 O CFR 20.203(d)(1

)(ii) defines an airborne radioactivity area as any room, . enclosure, or operating area in which airborne radioactive materials composed wholly or partly of licensed material exist in concentrations which, averaged over the number of hours in any week during which individuals are in the area, exceed 25 percent of the amounts specified in Appendix B, Table I, Column 1 of Part 20. Contrary to the requirements specified above, the. licensee failed to utilize, process or other engineering controls to the extent practical to limit airborne radioactivity material below 25 percent (1 O MPC-Hrs/Wk) of the amounts specified in Appendix B, Table I, Column 1, in that, between March 23-30, 1990, licensee personnel were in an average airborne concentration of 25 Hrs/Wk when the radioactivity concentration in the licensee's Auxiliary Building reached 99 times that specified in Appendix B, Table I, Column 1, of Part 20, on March 26, 1990. This is a severity level IV violation (Supplement IV).

  • RESPONSE TO NOTICE OF VIOLATION INSPECTION REPORT NOS. 50-280/90-18 AND 50-281/90-18 (1) ADMISSION OR DENIAL OF THE ALLEGED VIOLATION:

The violation is correct as stated. (2) REASONS FOR VIOLATION:

For a period of time prior to the loss of contamination control cited in this violation, a rubber hose had been in use to provide the dewatering flow path from the spent resin shipping containers in the Decontamination Building to a floor drain located in a high radiation area of the Auxiliary Building.

In addition, a contamination control barrier had been erected isolating this high radiation area of the Auxiliary Building.

As reported to the NRC inspector and documented in the Notice of Violation, on or about March 23, 1990, the floor drain backed up and drained leaving residual contamination which was the source of the airborne contamination detected in the Auxiliary Building on March 26, 1990. During the time of the loss of contamination control, several ventilation flow perturbations occurred in the area. Contributing to these perturbations were balance problems associated with the Auxiliary Building's ventilation system, the sealing of several ventilation flow paths in adjacent areas, and the running of a Fuel Building heating supply fan without operating the associated area . exhaust fans. When the High Radiation Area door was opened for personnel access, radioactive contamination in the higher pressure area was transported into the previously clean area. (3) CORRECTIVE STEPS WHICH HAVE BEEN TAKEN AND RESULTS ACHIEVED:

a. A permanent drain line has been installed and is in use for resin shipping container dewatering activities.
b. A matrix which describes proper ventilation alignment for different plant conditions has been prepared and provided to operating personnel for their use. ' c. The Auxiliary Building central and general ventilation exhaust systems have been balanced.
d. Station operating procedures have been changed to require that a temporary modification (TM) be performed and documented for the use of temporary hookups which will be used for handling radioactive process fluids. Such TMs are reviewed by Radiological Engineering and approved by SNSOC prior to initial use .
  • (4) CORRECTIVE STEPS WHICH WILL BE TAKEN TO AVOID FURTHER VIOLATIONS:

Additional walkdowns will be conducted to determine if other contamination control barriers exist which could, under certain ventilation configurations, permit a similar event to take place. Any such installations will be evaluated and modified as necessary.

(5) THE DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED:

System walkdowns will be completed and corrective actions will be implemented by September 30, 1990 .

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