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| number = ML20070G689 | | number = ML20070G689 | ||
| issue date = 07/13/1994 | | issue date = 07/13/1994 | ||
| title = Responds to NRC | | title = Responds to NRC Re Violations Noted in Insp Rept 50-483/93-14.Corrective Actions:Task Team Established to Define Course of Action to Correct Problems W/Rris | ||
| author name = Schnell D | | author name = Schnell D | ||
| author affiliation = UNION ELECTRIC CO. | | author affiliation = UNION ELECTRIC CO. | ||
| Line 11: | Line 11: | ||
| contact person = | | contact person = | ||
| document report number = ULNRC-3035, NUDOCS 9407200225 | | document report number = ULNRC-3035, NUDOCS 9407200225 | ||
| title reference date = 10-08-1993 | |||
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE | | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE | ||
| page count = 4 | | page count = 4 | ||
| Line 16: | Line 17: | ||
=Text= | =Text= | ||
{{#Wiki_filter:- | {{#Wiki_filter:- | ||
1901 Choutcaa Avenue Post Ot!;ce Bax 149 St iavis. Missouri 63166 314 554-2650 | 1901 Choutcaa Avenue Post Ot!;ce Bax 149 St iavis. Missouri 63166 314 554-2650 | ||
'Uuron July 13,1994 Donaldf Schnell Etscnuc sa: * ** | |||
33 U.S. Nuclear Regulatory Commission Document Control Desk | 33 U.S. Nuclear Regulatory Commission Document Control Desk i | ||
Washington, DC 20555 l | |||
ULNRC-3035 Gentlemen: | ULNRC-3035 Gentlemen: | ||
SUPPLEMENTAL RESPONSE TO NOTICE OF VIOLATION INSPECTION REPORT NO. 50-483/93014 CALLAWAY PLANT l | SUPPLEMENTAL RESPONSE TO NOTICE OF VIOLATION INSPECTION REPORT NO. 50-483/93014 CALLAWAY PLANT l | ||
l | l This provides the current status of corrective actions being taken in response to a Notice of Violations for events discussed in Inspection Report 50-483/93014. | ||
The notice was transmitted ir. Mr. William Snell's letter dated October 8,1993. | The notice was transmitted ir. Mr. William Snell's {{letter dated|date=October 8, 1993|text=letter dated October 8,1993}}. | ||
We responded by ULNRC-2901, dated November 2,1993. The current status and projected completion date for actions specified in our November response are presented in the attachment. | We responded by ULNRC-2901, dated November 2,1993. The current status and projected completion date for actions specified in our November response are presented in the attachment. | ||
l l | l l | ||
None of the material in the updated response is considered proprietary by Union i | |||
Electric Company. | |||
If you have any questions regarding this response, or if additional information is required, please let me know. | If you have any questions regarding this response, or if additional information is required, please let me know. | ||
l Ve truly yo | l Ve truly yo | ||
~ s ~ | |||
Donald F. Schnell DFS/tmw | Donald F. Schnell DFS/tmw | ||
==Attachment:== | ==Attachment:== | ||
: 1) Revised Response to Violation cc: | : 1) Revised Response to Violation cc: | ||
USNRC Document Control Desk (Original) | J. B. Martin - Regional Administrator, USNRC Region lli M. J. Farber - Chief, Reactor Projects Section 3C, USNRC Region lil L. R. Wharton - USNRC Licensing Project Manager (2 copies) | ||
USNRC Document Control Desk (Original) | |||
l | .] | ||
l Manager - Electric Department, Missouri Public Service Commission B. L. Bartlett - USNRC Senior Resident inspector j | |||
T. A. Baxter - Shaw, Pittman, Potts, and Trowbridge C. D. Pederson, Chief, Reactor Support Programs Branch i | |||
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'9407200225 940713 I | |||
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1 | I Attachm:nt to ULNRC-3035 j | ||
I | Page 1 of 3 t | ||
During an NRC inspection conducted on September 13 through 17,1993, three | Statement of Violations l | ||
During an NRC inspection conducted on September 13 through 17,1993, three violations of NRC requirements were identified. In accordance with the " General i | |||
Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, l | |||
l l | Appendix C, the violations are listed below: | ||
I | l l | ||
1. | |||
10 CFR 50.47 states, in part, that " adequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency condition are in use." | |||
I The Callaway Plant Radiological Emergency Response Plan states that "the l | |||
Radiological Release Information System (RRIS) provides near real-time predictions of atmospheric transport and diffusion estimates of radioactive releases." | |||
i Contrary to the above, on September 14,1993, the RRIS did not provide an accurate near real-time prediction of atmospheric transport and diffusion estimate of a radioactive release when its capabilities were demonstrated. | i Contrary to the above, on September 14,1993, the RRIS did not provide an accurate near real-time prediction of atmospheric transport and diffusion estimate of a radioactive release when its capabilities were demonstrated. | ||
This is a Severity Level IV violation (Supplement Vill). | This is a Severity Level IV violation (Supplement Vill). | ||
l | l 2. | ||
10 CFR 50.54(q) requires that a licensee authorized to possess and operate l | |||
a nuclear power reactor shall follow and maintain in effect emergency plans i which meet the standards in 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR Part 50. | a nuclear power reactor shall follow and maintain in effect emergency plans i | ||
The Callaway Radiological Emergency Response Plan, Section 8.1.1, states, in part, that periodic retraining is conducted to update the knowledge and l | which meet the standards in 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR Part 50. | ||
i l | The Callaway Radiological Emergency Response Plan, Section 8.1.1, states, in part, that periodic retraining is conducted to update the knowledge and l | ||
May 7,1993, for the Emergency Response Organization position of Dose Assessment Coordinator (DAC) was not effective in updating their knowledge l | skills of onsite personnel. | ||
l | i l | ||
Contrary to the above, periodic retraining of personnel provided on May 7,1993, for the Emergency Response Organization position of Dose Assessment Coordinator (DAC) was not effective in updating their knowledge l | |||
and skills in the functional use of the RRIS. | |||
l This is a Severity Level IV violation (Supplement Vill). | |||
l l | l l | ||
Attachmsnt to ULNRC-3035 Page 2 of 3 | Attachmsnt to ULNRC-3035 Page 2 of 3 3. | ||
10 CFR Part 50, Appendix E, Section F.5, states that."all training, including exercises, shall provide for formal critiques in order to identify weak or-deficient areas that need correction. Any weaknesses or deficiencies that are identified shall be corrected." | |||
Contrary to the above, no corrective actions were taken on' deficiencies identified for the Radiological Assessment Course, T68.1090.8, held on - | Contrary to the above, no corrective actions were taken on' deficiencies identified for the Radiological Assessment Course, T68.1090.8, held on - | ||
July 28,1992. | July 28,1992. | ||
This is a Severity Level IV violation (Suppiement Vill). | This is a Severity Level IV violation (Suppiement Vill). | ||
Status of Corrective Actions for Violation 1 A task team was established to define a course of action to correct problems identified with the RRIS. .While the team was reviewing options, it became clear that initial protective action recommendations (PARS) should be based directly on predefined plant parameters rather than dose calculations performed while an emergency is in progress. | Status of Corrective Actions for Violation 1 A task team was established to define a course of action to correct problems identified with the RRIS..While the team was reviewing options, it became clear that initial protective action recommendations (PARS) should be based directly on predefined plant parameters rather than dose calculations performed while an emergency is in progress. | ||
This change will require a revision to the Radiological Emergency Response Plan-prior to implementation. The revision will specify the following approach to developing Protective Action Recommendations: an Emergency implementing Procedure will be used by the On-Shift Emergency Response Organization to determine the appropriate PARS. The PARS will be based on the degree of core damage and loss of fission product barriers.' We will not require performance of dose calculations by the On-Shift Emergency Response Organization.10nce the Onsite and EOF Emergency Response Organizations have been mobilized,- dose assessment personnel will quantify the dose to the general public based on - | This change will require a revision to the Radiological Emergency Response Plan-prior to implementation. The revision will specify the following approach to developing Protective Action Recommendations: an Emergency implementing Procedure will be used by the On-Shift Emergency Response Organization to determine the appropriate PARS. The PARS will be based on the degree of core damage and loss of fission product barriers.' We will not require performance of dose calculations by the On-Shift Emergency Response Organization.10nce the Onsite and EOF Emergency Response Organizations have been mobilized,- dose assessment personnel will quantify the dose to the general public based on - | ||
effluent monitors, meteorological monitors, grab samples, and field monitoring team data. 'After tha data is obtained, dose assessment personnel will use a PC-based program to project doses to the general public and modify PARS as necessary. This program is in place and has been used previously'as a backup to the RRIS. | effluent monitors, meteorological monitors, grab samples, and field monitoring team data. 'After tha data is obtained, dose assessment personnel will use a PC-based program to project doses to the general public and modify PARS as necessary. This program is in place and has been used previously'as a backup to the RRIS. | ||
p 'J , i | p 'J, i 1 | ||
} | } | ||
1 | Att: chm!nt to l | ||
ULNRC-3035 i | |||
Page 3 of 3 i | |||
1[ | |||
Although the PC program does not meet all the characteristics of a C' lass A model as described in NUREG-0654, it does meet the criteria of NUREG/CR-2584 for i | |||
developing plume exposure pathway protective action recommendations. The j | |||
program has proven effective during training, drills and exercises. Also, dose l | |||
assessment personnel are proficient in its use. | |||
I j | |||
The RERP revision to implement this process will be submitted to the NRC for l | |||
review by September 15,1994. Following receipt of your approval, emergency i-implementing procedures will be revised within 30 days to incorporate the RERP.- | |||
changes. | |||
[ | [ | ||
Status of Corrective Actions for Violation 2 j[ | |||
As noted in our status of corrective actions for violation 1, the dose assessment program used at Callaway as a backup to the RRIS will be adapted to replace the - | |||
} | |||
' RRIS. This program was designed to eliminate the user interface limitations and.. | |||
complexity of the RRIS. Input data from the plant computer has been consolidated j | |||
As noted in our status of corrective actions for violation 1, the dose assessment | on accident-specific summary screens to facilitate data collection and transfer to the dose assessment program. | ||
} | The number of personnel maintaining qualification'for the Dose _ Assessment Coordinator position has been reduced to facilitate training and assure that they - | ||
!~ | |||
maintain a high level of capability. Dose as'sessment personnel have already l | |||
demonstrated proficiency using the PC-based program during past drills and l | |||
!~ | exercises. Additionally, all Dose Assessment Coordinators have successfully - | ||
l | l completed problem sets administered by the Training Department. | ||
1 l | 1 l | ||
We have completed all actions necessary to prevent recurrence. | |||
i | t i | ||
) | Status of Corrective Actions for Violation 3 The incorrect information in the action tracking system has been updated to show changes made as a result of student critiques from the July 28,1992 Radiological l | ||
results were discussed at a Training Department staff meeting with the | Assessment Course. | ||
i | |||
i j | ) | ||
A review of closed course deficiency items has shown that items are being closed j | |||
appropriately and the one uncorrected deficiency was an isolated case. These results were discussed at a Training Department staff meeting with the Superintendent, Training and Senior Training Supervisors! All were in agreement that additional training in the closure of Training Action Tracking items was not warranted. | |||
i j | |||
We have completed all actions necessary to prevent recurrence. | |||
J L | J L | ||
i}} | i}} | ||
Latest revision as of 09:40, 16 December 2024
| ML20070G689 | |
| Person / Time | |
|---|---|
| Site: | Callaway |
| Issue date: | 07/13/1994 |
| From: | Schnell D UNION ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| ULNRC-3035, NUDOCS 9407200225 | |
| Download: ML20070G689 (4) | |
Text
-
1901 Choutcaa Avenue Post Ot!;ce Bax 149 St iavis. Missouri 63166 314 554-2650
'Uuron July 13,1994 Donaldf Schnell Etscnuc sa: * **
33 U.S. Nuclear Regulatory Commission Document Control Desk i
Washington, DC 20555 l
ULNRC-3035 Gentlemen:
SUPPLEMENTAL RESPONSE TO NOTICE OF VIOLATION INSPECTION REPORT NO. 50-483/93014 CALLAWAY PLANT l
l This provides the current status of corrective actions being taken in response to a Notice of Violations for events discussed in Inspection Report 50-483/93014.
The notice was transmitted ir. Mr. William Snell's letter dated October 8,1993.
We responded by ULNRC-2901, dated November 2,1993. The current status and projected completion date for actions specified in our November response are presented in the attachment.
l l
None of the material in the updated response is considered proprietary by Union i
Electric Company.
If you have any questions regarding this response, or if additional information is required, please let me know.
l Ve truly yo
~ s ~
Donald F. Schnell DFS/tmw
Attachment:
- 1) Revised Response to Violation cc:
J. B. Martin - Regional Administrator, USNRC Region lli M. J. Farber - Chief, Reactor Projects Section 3C, USNRC Region lil L. R. Wharton - USNRC Licensing Project Manager (2 copies)
USNRC Document Control Desk (Original)
.]
l Manager - Electric Department, Missouri Public Service Commission B. L. Bartlett - USNRC Senior Resident inspector j
T. A. Baxter - Shaw, Pittman, Potts, and Trowbridge C. D. Pederson, Chief, Reactor Support Programs Branch i
"CL
'9407200225 940713 I
PDR ADOCK 0500o483
/
},
D.
-PDR:
t
~.
-,_.3 a
p
L, 1
I Attachm:nt to ULNRC-3035 j
Page 1 of 3 t
Statement of Violations l
During an NRC inspection conducted on September 13 through 17,1993, three violations of NRC requirements were identified. In accordance with the " General i
Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, l
Appendix C, the violations are listed below:
l l
1.
10 CFR 50.47 states, in part, that " adequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency condition are in use."
I The Callaway Plant Radiological Emergency Response Plan states that "the l
Radiological Release Information System (RRIS) provides near real-time predictions of atmospheric transport and diffusion estimates of radioactive releases."
i Contrary to the above, on September 14,1993, the RRIS did not provide an accurate near real-time prediction of atmospheric transport and diffusion estimate of a radioactive release when its capabilities were demonstrated.
This is a Severity Level IV violation (Supplement Vill).
l 2.
10 CFR 50.54(q) requires that a licensee authorized to possess and operate l
a nuclear power reactor shall follow and maintain in effect emergency plans i
which meet the standards in 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR Part 50.
The Callaway Radiological Emergency Response Plan, Section 8.1.1, states, in part, that periodic retraining is conducted to update the knowledge and l
skills of onsite personnel.
i l
Contrary to the above, periodic retraining of personnel provided on May 7,1993, for the Emergency Response Organization position of Dose Assessment Coordinator (DAC) was not effective in updating their knowledge l
and skills in the functional use of the RRIS.
l This is a Severity Level IV violation (Supplement Vill).
l l
Attachmsnt to ULNRC-3035 Page 2 of 3 3.
10 CFR Part 50, Appendix E, Section F.5, states that."all training, including exercises, shall provide for formal critiques in order to identify weak or-deficient areas that need correction. Any weaknesses or deficiencies that are identified shall be corrected."
Contrary to the above, no corrective actions were taken on' deficiencies identified for the Radiological Assessment Course, T68.1090.8, held on -
July 28,1992.
This is a Severity Level IV violation (Suppiement Vill).
Status of Corrective Actions for Violation 1 A task team was established to define a course of action to correct problems identified with the RRIS..While the team was reviewing options, it became clear that initial protective action recommendations (PARS) should be based directly on predefined plant parameters rather than dose calculations performed while an emergency is in progress.
This change will require a revision to the Radiological Emergency Response Plan-prior to implementation. The revision will specify the following approach to developing Protective Action Recommendations: an Emergency implementing Procedure will be used by the On-Shift Emergency Response Organization to determine the appropriate PARS. The PARS will be based on the degree of core damage and loss of fission product barriers.' We will not require performance of dose calculations by the On-Shift Emergency Response Organization.10nce the Onsite and EOF Emergency Response Organizations have been mobilized,- dose assessment personnel will quantify the dose to the general public based on -
effluent monitors, meteorological monitors, grab samples, and field monitoring team data. 'After tha data is obtained, dose assessment personnel will use a PC-based program to project doses to the general public and modify PARS as necessary. This program is in place and has been used previously'as a backup to the RRIS.
p 'J, i 1
}
Att: chm!nt to l
ULNRC-3035 i
Page 3 of 3 i
1[
Although the PC program does not meet all the characteristics of a C' lass A model as described in NUREG-0654, it does meet the criteria of NUREG/CR-2584 for i
developing plume exposure pathway protective action recommendations. The j
program has proven effective during training, drills and exercises. Also, dose l
assessment personnel are proficient in its use.
I j
The RERP revision to implement this process will be submitted to the NRC for l
review by September 15,1994. Following receipt of your approval, emergency i-implementing procedures will be revised within 30 days to incorporate the RERP.-
changes.
[
Status of Corrective Actions for Violation 2 j[
As noted in our status of corrective actions for violation 1, the dose assessment program used at Callaway as a backup to the RRIS will be adapted to replace the -
}
' RRIS. This program was designed to eliminate the user interface limitations and..
complexity of the RRIS. Input data from the plant computer has been consolidated j
on accident-specific summary screens to facilitate data collection and transfer to the dose assessment program.
The number of personnel maintaining qualification'for the Dose _ Assessment Coordinator position has been reduced to facilitate training and assure that they -
!~
maintain a high level of capability. Dose as'sessment personnel have already l
demonstrated proficiency using the PC-based program during past drills and l
exercises. Additionally, all Dose Assessment Coordinators have successfully -
l completed problem sets administered by the Training Department.
1 l
We have completed all actions necessary to prevent recurrence.
t i
Status of Corrective Actions for Violation 3 The incorrect information in the action tracking system has been updated to show changes made as a result of student critiques from the July 28,1992 Radiological l
Assessment Course.
i
)
A review of closed course deficiency items has shown that items are being closed j
appropriately and the one uncorrected deficiency was an isolated case. These results were discussed at a Training Department staff meeting with the Superintendent, Training and Senior Training Supervisors! All were in agreement that additional training in the closure of Training Action Tracking items was not warranted.
i j
We have completed all actions necessary to prevent recurrence.
J L
i