View source for LIC-02-0115, LER 02-S01-00 for Fort Calhoun Unit 1 Regarding Possible Error in Classification of Safeguards Material on September 6, 2002

{{Adams
| number = ML022900492
| issue date = 10/04/2002
| title = LER 02-S01-00 for Fort Calhoun Unit 1 Regarding Possible Error in Classification of Safeguards Material on September 6, 2002
| author name = Bannister D
| author affiliation = Omaha Public Power District
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000285
| license number = DPR-040
| contact person = 
| case reference number = LIC-02-0115
| document report number = LER 02-S01-00
| document type = Licensee Event Report (LER)
| page count = 3
}}

=Text=
{{#Wiki_filter:Opp"
          *m       m Omaha Pubhc Power DOstnct 444 South 16th Street Mall Omaha NE 68102-2247 October 4, 2002 LIC-02-0115 U. S. Nuclear Regulatory Commission Attn: Document Control Desk_
Mail Station P1-137 Washington, DC 20555

==Reference:==
Docket No. 50-285

==Subject:==
Licensee Event Report 2002-SO1 Revision 0 for the Fort Calhoun Station I  '..,'.2     _*.. .   .2 Please find attached'Licensee Event Report 2002-S01, Revision 0, dated October 4, 2002. This report is being submitted, pursuant-to 10 CFR 73.71(a)(4). This document does not contain any safeguards material. No commitments are made to the NRC in this letter.
If you should have any questions, please contact me.
Sincerely, D. J. Bannister Manager, Fort Calhoun Station 4i              DJB/EPM/epm
  'I S-         Attachment c:          E. W. Merschoff, NRC Regional Administrator, Region IV A. B. Wang, NRC Project Manager J. G. Kramer, NRC Senior Resident Inspector,         ..     .,....   .
                            .INPO.Records Center-                    ,  .J                      ..4.        "
Winston and Strawn
                                                    *    * ' ,..                            3/4' Employment with Equal Opportunity                                                                         4171

NRCLFORM 366                            U.S. NUCLEAR REGULATORY                        APPROVED BY OMB NO. 3150-0104 EXPIRES 7-31-2004 (7-2oDOj                                                      COMMISSION               Esimatedrburden per response to comply with this mandatory information collection request 50 hours Reported lessons learned are incorporated Into the licensing process and fed back to industry Send comments regarding burden estimate to the Records Management Branch LICENSEE EVENT REPORT (LER)                                              (T-6 E6),U S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by Internet e mail to bjsl@nrc gov, and to the Desk Officer, Office of Information and Regulatory Affairs, (See reverse for required number of                                  NEOB-10202 (3150-0104), Office of Management and Budget, Washington, DC 20503 If a digits/characters for each block)                                 means used to Impose Information collection does not display a currently valid 0MB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the Information collection
: 1. FACILITY NAME                                                                          DOCKETNUMBER                                                    3. PAGE Fort Calhoun Nuclear Station Unit Number 1                                                               05000285                                            OF    2
: 4. TITLE Possible Error in Classification of Safeguards Material
: 5. EVENT DATE                      6. LER NUMBER                   7. REPORT DATE                                 6. OTHER FACILITIES INVOLVED I SEQUENTIAL. REV        MO           DAY       YEAR       FACILITY NAME                DOCKET NUMBER MO             DAY      YEAR     YEAR         NUMBER       NO                                                                          05000 FACILITY NAME                DOCKET NUMBER 09             06       2002     2002 - S01             -  00       10          04        2002                                         05000
: 9. OPERATING                1  -            11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR &sect;: (Check all that apply)
MODE                    -        20.2201(b)                    20 2203(a)(3)(i)                       50.73(a)(2)(ii(B)             50.73(a)(2)(ix)(A)
: 10. POWER               _100o       20 2201(d)                    20.2203(a)(4)                          50 73(a)(2)(iii)              50 73(a)(2)(x)
      -   LEVEL--                            20.2203(a)      --           50-36c)(1)6        )(A)         -      50.73(a)(2)(rv)(A)    -- X    73.71(a)(4)
_    20.2203(a)(2)(i)              50 36(c)(1)(ii)(A)                     50.73(a)(2)(v)(A)             73.71 (a)(5) 20.2203(a)(2)(i)              50 36(c)(2)                            50.73(a)(2)(v)(B)             OTHER 20 2203(a)(2)(iU)             50 46(a)(3)(ii)                        50.73(a)(2)(v)(C)             Specify in Abstract below or in "20.2203(a)(2)(iv)            50 73(a)(2)(i)(A)                      50.73(a)(2)(v)(D)             NRC Form 366A 20 2203(a)(2)(v)             50.73(a)(2)(i)(B)                      50 73(a)(2)(vii)
__20   2203(a)(2)(vi)      _50.73(a)(2)(i)(C)                          50 73(a)(2)(vii)(A)
______________________-____;*:!            20 2203(a)(3)(I)             50 73(a)(2)(ii)(A)                     50 73(a)(2)(viii)(B)
: 12. LICENSEE CONTACT FOR THIS LER NAME                                                                                                        TELEPHONE NUMBER (include Area Code)
Erick Matzke, Licensing Engineer                                                                                                    (402) 533-6855
: 13. COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT CAUSE          S SYSTEM C
COMPONEN MANU-FACTURER REPORTABLE TO EPIX I      CAUSE SYSTEM          COMPONENT           MANU-FACTURER REPORTABLE TO EPIX
: 14. SUPPLEMENTAL REPORT EXPECTED                                                         15. EXPECTED            MONTH          DAY           YEAR SUBMISSION FYES (If yes, complete EXPECTED SUBMISSION DATE).                                 X     NO                         DATE
: 16. ABSTRACT (Limit to 1400 spaces, i e., approximately 15 single-spaced typewritten lines)
On September 6, 2002, following a review of the approved Abnormal Operating Procedure (AOP) -37, "Security Events," NRC Region IV staff raised an issue regarding information in the procedure. The NRC Staff informed OPPD management that they considered information contained in AOP-37 as Safeguards Information
   -(SGI)Th-e NRC'Stff has-di&sect;-u-s-sed that thr-c--rh~il~tion-of tlis&sect;typ0f info'rmnation int6-one &#xfd;ioted~rre-is-vWhat drives them to the conclusion that AOP-37 is SGI.
As a conservative measure, Fort Calhoun Station personnel took immediate action to ensure that the procedure was controlled as SGI, and made a 10 CFR 73.71 report to the NRC on September 6, 2002.
The Omaha Public Power District (OPPD) is discussing this issue with NRC Region IV Staff. It is OPPD's understanding that the NRC regional staff is still determining the correct classification of the document. OPPD will update or cancel this LER as appropriate when the classification of this document has been resolved.
NRC FORM 366 (7-2001)

NRC FORM 363A                                                                                 U.S. NUCLEAR REGULATORY COMMISSION (1-2001)
LICENSEE EVENT REPORT (LER)
: 1. FACILITY NAME                      2. DOCKET                6. LER NUMBER                  3. PAGE YEAR         SEQUENTIAL    REVISION Fort Calhoun Nuclear Station Unit Number 1                 05000285                         NUMBER       NUMBER  2     OF     2 2002       -    S01           00
: 17. NARRATIVE (If more space is required,use additionalcopies of NRC Form 366A)
BACKGROUND In November 2001, FCS personnel reviewed and approved Abnormal Operating Procedure (AOP) -37, "Security Events." As part of the review process used to approve the procedure, the Omaha Public Power District (OPPD) reviewed AOP-37 using an information classification procedure for security issues. This classification procedure, Nuclear Operations Division (NOD) Quality Procedure (QP) -14, "Protection of Safeguards Information," provides guidance to determine the classification of documents that may contain safeguards information. Key provisions of NOD-QP-14 were generated based upon information in a July 23, 1991 letter
  -from the-NRC-Director of-NRR-to-the NRC-Region-Administrators.--                ..            ...-  ..
During a security event, operations personnel and security officers must communicate effectively. A procedure (AOP-37) needed to'be developed that would provide a tie for operations (that use room numbers) to the security officers (that use door numbers) to effectively communicate plant locations to one another.
OPPD fashioned AOP-37 to be useful to the operators during potential security events without creating the need to employ safeguards controls to operate the plant EVENT DESCRIPTION On September 6, 2002, following a review of the approved AOP-37, NRC Region IV staff raised an issue regarding information in the procedure. The NRC Staff informed OPPD management that they considered information contained in AOP-37 as Safeguards Information (SGI). The NRC Staff has discussed that the compilation of this type of information into one procedure is what drives them to the conclusion that AOP-37 is SGI.
As a conservative measure, FCS personnel took immediate action to ensure that the procedure was controlled as SGI, and made a 10 CFR 73.71 report to the NRC on September 6, 2002.
CONCLUSION OPPD is currently discussing this issue with NRC Region IV Staff. It is OPPD's understanding that the NRC regional staff is still determining the correct classification of the document. OPPD will update or cancel this
 ._LER-as appropriate when the classification.of-this-document has.been-resolved.-                                           -
NRC FORM 366A (1-2001)}}