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  .. O                                       JUN 131986
.. O
                                                                                                                    .
JUN 131986
.
-
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          ' Docket Nos. 50-317                                             License Nos. DPR-53
License Nos. DPR-53
                          50-318                                                                       DPR-69
' Docket Nos. 50-317
            Baltimore Gas and Electric Company
50-318
            ATTN: Mr. J. A. Tiernan
DPR-69
                    Vice President
Baltimore Gas and Electric Company
                    Nuclear ~ Energy
ATTN: Mr. J. A. Tiernan
            P.O. Box 1475
Vice President
            Baltimore, Maryland 21203
Nuclear ~ Energy
            Gentlemen:
P.O. Box 1475
          -Subject:     Inspection.Nos. 50-317/86-05 and 50-318/86-05
Baltimore, Maryland 21203
            This refers to your letter dated May 17, 1986, in response to our letter dated
Gentlemen:
            April.17, 1986.
-Subject:
                                                                                                                            '
Inspection.Nos. 50-317/86-05 and 50-318/86-05
            Thank you for. informing us of.the corrective and preventive actions documented                                 '
This refers to your letter dated May 17, 1986, in response to our letter dated
            in your letter. These actions will be examined .during a future inspection of
April.17, 1986.
            your. licensed program.
'
            With regard to Item A, we have; reviewed your. audit report, dated April '17,
Thank you for. informing us of.the corrective and preventive actions documented
          ~1986, for -the- Quality Assurance Audit -QAP-8 (Dosimetry and Respiratory-
'
          : Protection) performed February 11 through March 17, 1986. This audit includes
in your letter. These actions will be examined .during a future inspection of
            Finding Number 86-09-02, failure to have an approved procedure for operation
your. licensed program.
            of the standup whole body counter. Although this audit was ongoing during our
With regard to Item A, we have; reviewed your. audit report, dated April '17,
            inspection of March 3-7, 1986, it was not documented until after completion of
~1986, for -the- Quality Assurance Audit -QAP-8 (Dosimetry and Respiratory-
          -our inspection.         Discussion by the NRC Resident Inspector with the QA auditor                             i
: Protection) performed February 11 through March 17, 1986. This audit includes
            on May 28, 1986, indicated that this item was identified prior to the- begin-
Finding Number 86-09-02, failure to have an approved procedure for operation
            ning of our inspection. Therefore, Item A meets all of the requirements of 10
of the standup whole body counter. Although this audit was ongoing during our
            CFR 2,' Appendix C, for a violation for which -the NRC will not generally issue:
inspection of March 3-7, 1986, it was not documented until after completion of
                                          -
-our inspection.
            a notice of violation: -(1) it was identified by the licensee; (2) it fits in:
Discussion by the NRC Resident Inspector with the QA auditor
          -Severity Level IV or V; (3)-it was reported, if required; (4) it was or will
i
            be corrected, -including measures to prevent recurrence, within a reasonable
on May 28, 1986, indicated that this item was identified prior to the- begin-
            time; and (5) it was not a violation that could-reasonably be expected to have
ning of our inspection. Therefore, Item A meets all of the requirements of 10
          .been prevented _ by the licensee's corrective action for a previous violation.
CFR 2,' Appendix C, for a violation for which -the NRC will not generally issue:
            Item A is retracted. We will modify.our records accordingly.
-
            Your cooperation with us is appreciated.
a notice of violation: -(1) it was identified by the licensee; (2) it fits in:
                                                            Sincerely,
-Severity Level IV or V; (3)-it was reported, if required; (4) it was or will
                                                        'origfrel Signed Dpt
be corrected, -including measures to prevent recurrence, within a reasonable
                                                          Th0Cas T. Martin
time; and (5) it was not a violation that could-reasonably be expected to have
                              . -
.been prevented _ by the licensee's corrective action for a previous violation.
                                                            Thomas T. Martin, Director.
Item A is retracted. We will modify.our records accordingly.
          8606190348 860613                                 Division of Radiation Safety
Your cooperation with us is appreciated.
            DR    ADOCK0500g7                                 and Safeguards
Sincerely,
                                                                                                                      [[k
'origfrel Signed Dpt
                                                                                                                        ' '
Th0Cas T. Martin
                                              0FFICIAL' RECORD COPY
. -
                                                                                    . _ - . _ _ . _ . _ _ . _ _ _ _ .
Thomas T. Martin, Director.
8606190348 860613
Division of Radiation Safety
ADOCK0500g7
and Safeguards
DR
[[k
' '
0FFICIAL' RECORD COPY
.
- .
.
.
.
.


  $-                                                                               l
$-
        Baltimore Gas                           2
Baltimore Gas
  i     and Electric Company
2
        cc :
i
      M. Bowman, General Supervisor, Technical Services Engineering
and Electric Company
        Thomas Magette, Administrator, Nuclear Evaluations
cc :
        Daniel Latham, Director, Security Services (Safeguards Only)
M. Bowman, General Supervisor, Technical Services Engineering
        Norman J. Bowmaker, Vice President, General Services (Safeguards Only)
Thomas Magette, Administrator, Nuclear Evaluations
        Public Document Room (PDR)
Daniel Latham, Director, Security Services (Safeguards Only)
        Local Public Document Room (LPDR)
Norman J. Bowmaker, Vice President, General Services (Safeguards Only)
        Nuclear Safety Information Center (NSIC)
Public Document Room (PDR)
        NRC Resident Inspector
Local Public Document Room (LPDR)
        State of Maryland (2)
Nuclear Safety Information Center (NSIC)
        bec :
NRC Resident Inspector
        Region I Docket Room (with concurrences)
State of Maryland (2)
      Management Assistant, DRMA (w/o encl)
bec :
      DRP Section Chief
Region I Docket Room (with concurrences)
      M. McBride, RI, Pilgrira
Management Assistant, DRMA (w/o encl)
      T. Kenny, SRI, Salem
DRP Section Chief
      D. Jaffe, LPM, NRR
M. McBride, RI, Pilgrira
      k
T. Kenny, SRI, Salem
      [RSS:RI               :RI
D. Jaffe, LPM, NRR
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DR : RI
                                  0FFICIAL RECORD COPY     RL CC 86-05 - 0002.0.0
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                                                            06/06/86
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            *
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  .   ,. .
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                                                              -
.
  a,                                     .
.
                                                        BALTIMORE
-
                                                        GAS AND
a,
    3
.
                                                        ELECTRIC
BALTIMORE
                                  CHARLES CENTER P. O. BOX 1475 BALTIMORE MARYLAND 21203
GAS AND
            JOSEPH A.TIERNAN
ELECTRIC
                VicE PREslOENT
3
                NUCLEAR ENEROY
CHARLES CENTER P. O. BOX 1475 BALTIMORE MARYLAND 21203
                                                                        May 17,1986
JOSEPH A.TIERNAN
            U. S. Nuclear Regulatory Commission                                 License Nos.   DPR-53
VicE PREslOENT
            Region I                                                                           DPR-69
NUCLEAR ENEROY
            631 Park Avenue                                                     Docket Nos.     50-317
May 17,1986
            King of Prussia, PA 19406                                                           50-318
U. S. Nuclear Regulatory Commission
            ATTENTION:           Mr. Thomas T. Martin, Director
License Nos.
                                  Division of Radiation Safety and Safeguards
DPR-53
            Gentlemen:
Region I
            This refers to inspection Report 50-317/86-05 and 50-318/86-05, which transmitted two
DPR-69
              items of apparent noncompliance with NRC requirements. Enclosure (1) to this letter is
631 Park Avenue
            a written statement in reply to those items noted in your letter of April 17, 1986.
Docket Nos.
50-317
King of Prussia, PA 19406
50-318
ATTENTION:
Mr. Thomas T. Martin, Director
Division of Radiation Safety and Safeguards
Gentlemen:
This refers to inspection Report 50-317/86-05 and 50-318/86-05, which transmitted two
items of apparent noncompliance with NRC requirements. Enclosure (1) to this letter is
a written statement in reply to those items noted in your letter of April 17, 1986.
.
.
              Should you have further questions regarding this reply, we will be pleased to discuss them
Should you have further questions regarding this reply, we will be pleased to discuss them
!             with you.
!
with you.
l
l
Very truly yours,
'
'
                                                                      Very truly yours,
i
i
f
f
l             JAT/SRC/ dim
l
              Enclosure
JAT/SRC/ dim
              cc:     D. A. Brune, Esquire
Enclosure
i                     J. E. Silberg, Esquire
cc:
D. A. Brune, Esquire
i
J. E. Silberg, Esquire
'
'
                      D. H. Jaffe, NRC
D. H. Jaffe, NRC
                      T. Foley, NRC
T. Foley, NRC
l
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  . ., .
. .,
  -                                                      -
.
                                    .  .
.
                                                ENCLOSURE (1)
.
  l
-
                                      REPLY TO APPENDIX A OF NRC
-
                              INSPECTION REPORT 50-317/86-05; 50-318/86-05
ENCLOSURE (1)
          ITEM A
          At the time of the inspection, the computerized chest counter was in use to supplement
          approved procedures for identifying personnel having potential internal contamination.
          The chest counter identifies those personnel whose counts are statistically greater than
          background levels and instructs the operator to perform, as necessary, whole body counts
          using an approved procedure in accordance with Technical Specification 6.8.1.a. The
          chest counter was not used to perform analytical measurements to assess internal
          intakes.
          This use of a draft procedure was identified as a deficiency by the Baltimore Gas and
          Electric (BG&E) Company prior to the inspection during a recent Quality Assurance
          audit. This fact was communicated by Mr. E. H. Roach of our staff, to Mr. J. J. Kottan
          of your staff, prior to the exit meeting. A commitment was made to our internal Quality
          Assurance organization prior to the NRC inspection to formalize the procedure for the
          operation of the chest counter. This draf t procedure will be approved and implemented
          by June 1,1986. Because this is a licensee-identified item, which will be corrected under
          existing BG&E programs, and because we believe this screening procedure is not required
          to comply with existing regulations, we request you reconsider issuing the subject
          violation.
l          ITEM B
l
l
          We have reviewed the circumstances that led to the apparent violation of Technical
REPLY TO APPENDIX A OF NRC
l         Specifications 4.6.3.1, 4.6.6.1, 4.7.6.1, 4.7.7.1, and 4.9.12. This event was caused by an
INSPECTION REPORT 50-317/86-05; 50-318/86-05
          apparent misinterpretation of the Surveillance Requirements and a miscommunication
ITEM A
          with the contractor involved. Accordingly, the corrective action stated below will be
At the time of the inspection, the computerized chest counter was in use to supplement
          implemented to ensure that similar violations will not recur in the future.
approved procedures for identifying personnel having potential internal contamination.
          The appropriate procedures will be revised to ensure that two separate samples are
The chest counter identifies those personnel whose counts are statistically greater than
          analyzed in accordance with the Surveillance Requirements. In addition, our contracts
background levels and instructs the operator to perform, as necessary, whole body counts
          with outside laboratories will be altered to ensure that two distinct laboratory analyses
using an approved procedure in accordance with Technical Specification 6.8.1.a.
          are performed. These changes will be made by September 1,1986.
The
          Furthermore, we are considering submitting a license amendment request that changes
chest counter was not used to perform analytical measurements to assess internal
          the applicable Technical Specifications such that only one analysis is required of the
intakes.
          charcoal sample. The procedures will then be revised again if a new Surveillance
This use of a draft procedure was identified as a deficiency by the Baltimore Gas and
          Requirement is issued.
Electric (BG&E) Company prior to the inspection during a recent Quality Assurance
                                                        .
audit. This fact was communicated by Mr. E. H. Roach of our staff, to Mr. J. J. Kottan
of your staff, prior to the exit meeting. A commitment was made to our internal Quality
Assurance organization prior to the NRC inspection to formalize the procedure for the
operation of the chest counter. This draf t procedure will be approved and implemented
by June 1,1986. Because this is a licensee-identified item, which will be corrected under
existing BG&E programs, and because we believe this screening procedure is not required
to comply with existing regulations, we request you reconsider issuing the subject
violation.
l
ITEM B
l
We have reviewed the circumstances that led to the apparent violation of Technical
l
Specifications 4.6.3.1, 4.6.6.1, 4.7.6.1, 4.7.7.1, and 4.9.12. This event was caused by an
apparent misinterpretation of the Surveillance Requirements and a miscommunication
with the contractor involved. Accordingly, the corrective action stated below will be
implemented to ensure that similar violations will not recur in the future.
The appropriate procedures will be revised to ensure that two separate samples are
analyzed in accordance with the Surveillance Requirements. In addition, our contracts
with outside laboratories will be altered to ensure that two distinct laboratory analyses
are performed. These changes will be made by September 1,1986.
Furthermore, we are considering submitting a license amendment request that changes
the applicable Technical Specifications such that only one analysis is required of the
charcoal sample.
The procedures will then be revised again if a new Surveillance
Requirement is issued.
.
..
.
.
-
-
}}
}}

Latest revision as of 03:26, 24 May 2025

Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insps 50-317/86-05 & 50-318/86-05.Retracts Item a Re Dosimetry & Respiratory Protection
ML20199D132
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 06/13/1986
From: Martin T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Tiernan J
BALTIMORE GAS & ELECTRIC CO.
References
NUDOCS 8606190348
Download: ML20199D132 (2)


See also: IR 05000317/1986005

Text

{{#Wiki_filter:.. 4 .. O JUN 131986 . - License Nos. DPR-53 ' Docket Nos. 50-317 50-318 DPR-69 Baltimore Gas and Electric Company ATTN: Mr. J. A. Tiernan Vice President Nuclear ~ Energy P.O. Box 1475 Baltimore, Maryland 21203 Gentlemen: -Subject: Inspection.Nos. 50-317/86-05 and 50-318/86-05 This refers to your letter dated May 17, 1986, in response to our letter dated April.17, 1986. ' Thank you for. informing us of.the corrective and preventive actions documented ' in your letter. These actions will be examined .during a future inspection of your. licensed program. With regard to Item A, we have; reviewed your. audit report, dated April '17, ~1986, for -the- Quality Assurance Audit -QAP-8 (Dosimetry and Respiratory-

Protection) performed February 11 through March 17, 1986. This audit includes

Finding Number 86-09-02, failure to have an approved procedure for operation of the standup whole body counter. Although this audit was ongoing during our inspection of March 3-7, 1986, it was not documented until after completion of -our inspection. Discussion by the NRC Resident Inspector with the QA auditor i on May 28, 1986, indicated that this item was identified prior to the- begin- ning of our inspection. Therefore, Item A meets all of the requirements of 10 CFR 2,' Appendix C, for a violation for which -the NRC will not generally issue: - a notice of violation: -(1) it was identified by the licensee; (2) it fits in: -Severity Level IV or V; (3)-it was reported, if required; (4) it was or will be corrected, -including measures to prevent recurrence, within a reasonable time; and (5) it was not a violation that could-reasonably be expected to have .been prevented _ by the licensee's corrective action for a previous violation. Item A is retracted. We will modify.our records accordingly. Your cooperation with us is appreciated. Sincerely, 'origfrel Signed Dpt Th0Cas T. Martin . - Thomas T. Martin, Director. 8606190348 860613 Division of Radiation Safety ADOCK0500g7 and Safeguards DR [[k ' ' 0FFICIAL' RECORD COPY . - . . . . .

$- Baltimore Gas 2 i and Electric Company cc : M. Bowman, General Supervisor, Technical Services Engineering Thomas Magette, Administrator, Nuclear Evaluations Daniel Latham, Director, Security Services (Safeguards Only) Norman J. Bowmaker, Vice President, General Services (Safeguards Only) Public Document Room (PDR) Local Public Document Room (LPDR) Nuclear Safety Information Center (NSIC) NRC Resident Inspector State of Maryland (2) bec : Region I Docket Room (with concurrences) Management Assistant, DRMA (w/o encl) DRP Section Chief M. McBride, RI, Pilgrira T. Kenny, SRI, Salem D. Jaffe, LPM, NRR k 41 S h [RSS:RI

RI

DRSS:RI DR : RI DRSS:RI DR .RI Kottan/pj /t,Kramaric Miller Pas ak Bellamy M rtin 6/b /86 6/(,/86 6/6/86 6/4 /86 6/4 /86 6//t./86 0FFICIAL RECORD COPY RL CC 86-05 - 0002.0.0 06/06/86 4 . ... - ,,,

,. . . - a, . BALTIMORE GAS AND ELECTRIC 3 CHARLES CENTER P. O. BOX 1475 BALTIMORE MARYLAND 21203 JOSEPH A.TIERNAN VicE PREslOENT NUCLEAR ENEROY May 17,1986 U. S. Nuclear Regulatory Commission License Nos. DPR-53 Region I DPR-69 631 Park Avenue Docket Nos. 50-317 King of Prussia, PA 19406 50-318 ATTENTION: Mr. Thomas T. Martin, Director Division of Radiation Safety and Safeguards Gentlemen: This refers to inspection Report 50-317/86-05 and 50-318/86-05, which transmitted two items of apparent noncompliance with NRC requirements. Enclosure (1) to this letter is a written statement in reply to those items noted in your letter of April 17, 1986. . Should you have further questions regarding this reply, we will be pleased to discuss them ! with you. l Very truly yours, ' i f l JAT/SRC/ dim Enclosure cc: D. A. Brune, Esquire i J. E. Silberg, Esquire ' D. H. Jaffe, NRC T. Foley, NRC l , b h0hk~7C71Q~ - - -

. ., . . . - - ENCLOSURE (1) l REPLY TO APPENDIX A OF NRC INSPECTION REPORT 50-317/86-05; 50-318/86-05 ITEM A At the time of the inspection, the computerized chest counter was in use to supplement approved procedures for identifying personnel having potential internal contamination. The chest counter identifies those personnel whose counts are statistically greater than background levels and instructs the operator to perform, as necessary, whole body counts using an approved procedure in accordance with Technical Specification 6.8.1.a. The chest counter was not used to perform analytical measurements to assess internal intakes. This use of a draft procedure was identified as a deficiency by the Baltimore Gas and Electric (BG&E) Company prior to the inspection during a recent Quality Assurance audit. This fact was communicated by Mr. E. H. Roach of our staff, to Mr. J. J. Kottan of your staff, prior to the exit meeting. A commitment was made to our internal Quality Assurance organization prior to the NRC inspection to formalize the procedure for the operation of the chest counter. This draf t procedure will be approved and implemented by June 1,1986. Because this is a licensee-identified item, which will be corrected under existing BG&E programs, and because we believe this screening procedure is not required to comply with existing regulations, we request you reconsider issuing the subject violation. l ITEM B l We have reviewed the circumstances that led to the apparent violation of Technical l Specifications 4.6.3.1, 4.6.6.1, 4.7.6.1, 4.7.7.1, and 4.9.12. This event was caused by an apparent misinterpretation of the Surveillance Requirements and a miscommunication with the contractor involved. Accordingly, the corrective action stated below will be implemented to ensure that similar violations will not recur in the future. The appropriate procedures will be revised to ensure that two separate samples are analyzed in accordance with the Surveillance Requirements. In addition, our contracts with outside laboratories will be altered to ensure that two distinct laboratory analyses are performed. These changes will be made by September 1,1986. Furthermore, we are considering submitting a license amendment request that changes the applicable Technical Specifications such that only one analysis is required of the charcoal sample. The procedures will then be revised again if a new Surveillance Requirement is issued. . .. . . - - }}