IR 05000285/1987031

Insp Rept 50-285/87-31 on 871116-19.No Violations or Deviations Noted.Major Areas Inspected:Emergency Detection & Classification,Protective Action Decisionmaking, Notifications & Communication & Shift Staffing

ML20237E403
Person / Time
Site:	Fort Calhoun
Issue date:	12/08/1987
From:	Fisher W, Terc N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20237E391	List: IR 05000285/1987031 ML20237E390
References
50-285-87-31, NUDOCS 8712280314
Download: ML20237E403 (5)

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I APPENDIX U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report: 50-285/87-31 Operating License: DPR-40 l j

Docket: 50-285 Licensee: Omaha Public Power District (OPPD) l 1623 Harney Street Omaha, Nebraska 68102  ;

i Facility Name: Fort Calhoun Station (FCS) I Inspection At: FCS, Omaha and Fort Calhoun, Nebraska l

l Inspection Conducted: November 16-19, 1987 l

Inspector: ) b% A bA '

/,L [f ~/<f 7 Nemen M. Terc, Emergency Preparedness Date Specialist Approved: 1, . [o- s u th[Lv L JI/.T/C 7 Wil'iiam L. Fisher, Chief, Nuclear Materials Date and Emergency Preparedness Branch Inspection Summary Inspection Conducted November 16-19, 1987 (Report 50-285/87-31) i Areas Inspected: Routine, unannounced inspection of emergency detection and classification, protective action decisionmaking, notifications and communications, and shift staffing and augmentatio Results: Within the areas inspected, no violations or deviations were identifie h22kDO p G

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DETAILS Persons Contacted Licensee

• R. L. Andrews, Division Manager, Nuclear Production

• G. Gates, Manager, Fort Calhoun Statio *F. Franco, Manager, Radiation Health and Emergency Preparedness

• A. Richard, Manager, Quality Assurance

• J. Gasper, Manager, Administrative'and Training Services

• R. Jaworski, Section Manager, Technical Services Others P..Harrell, NRC Senior Resident Inspector

• Denotes-those in attendance at the exit intervie . Followup On Previous Inspection Findings (Closed) Deficiency (285/8516-01): Internal Inconsistencies In Exercise Scenario - The NRC inspector determined that some progress was made in scenario. development and that a new procedure.for developing scenarios was issued in 1987. However, additional scenario weaknesses were identified in the July 1987 exercise. This item is being followed up by item No. 285/8719-0 (Closed) Deficiency (285/8719-02): Inadequate Notifications Procedure -

The NRC inspector verified that a-new procedure, EPIP-050-2, " Emergency Plan Activation and Notifications," had been written and approved. The NRC inspector reviewed the procedure and determined that it-incorporated changes to remove previous inconsistencies and to add new instructions reflecting the new simultaneous paging syste (Closed) Deficiency (285/8620-01):, Lack Of An Atmospheric Filtration Testing Program For The Technical Support Center (TSC) - The NRC inspector noted that on July 30, 1987, the licensee had approved and issued Procedure No. PM-FI-4," Charcoal /HEPA filter bank in place leak testing of TSC air filtration system." This procedum established a; routine program to verify the design criterion filtration efficienc (Closed)UnresolvedItem(285/8620-04): Accumulator Tank' Level and Pressure Variables - (See Open Item 285/8731-01 below.)

(0 pen)OpenItem(285/8731-01): _ Accumulator Tank Level and Pressure Variables - The NRC inspector determined.that, according to an April 22,.

1987, letter from W. A. Paulson of the Division of Reactor Projects, NR _ _ _ _ _ _ - - _ - _ _ _ - _ _ _ _ _ _ _ _ _ - __ _ _ - - _ - - _ _ _ _

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i to R. L. Andrews, Division Manager-Nuclear Production, pertaining to OPPD's conformance to Regulatory Guide 1.97, Revision 2, the NRC staff does not find this item acceptable. A generic review will be made by the NRC staff for establishing the need for environmentally qualified Category 2 instruments to monitor these variables. This item will remain open pending the completion of the review by the NRC staf (0 pen)UnresolvedItem(285/8620-05): Deficient Instrumentation For Measuring Containment Sump Water Temperature - The NRC inspector noTed that, according to records, tTie deadline for this item was extended by NRC until the end of the 1988 refueling outag (Closed) Unresolved Item (285/8620-06): Instrumentation not Environmentally Oualified - The NRC inspector determined that although

, installation of environmentally qualified instrumentation for measuring I temperature and flow of component cooling water to the emergency safety l system was completed in June 1987, this instrumentation is not required to be environmentally qualified because instruments are located in a mild environmen (Closed)UnresolvedItem(285/8620-07): Deficient Wind Direction Accuracy - The NRC inspector determined by review of existing documentation that an accuracy of 5 percent for wind direction was now available.

l (Closed) Unresolved Item (285/8620-08): Lack Of Continous Reactor Vessel Water Level Indicator - The NRC inspector verified that the Emergency Response Facilities Computer System in the control room displayed a continuous range of the water level which included the range from the top of the core to the top of the reactor vesse (Closed) Unresolved Item (285/8620-09): Lack Of 0xygen Content Measurement In Post Accident Sampling System (PASS) - Enclosure 1 of April 72, 1987, hRL letter quoted above (see Unresolved Item 285/8620-04)

stated that measurement of oxygen content is not required, since the containment at FCS is not purged and inerte (Closed) Unresolved Item (285/8620-10): Inadequate Isolation - The NRC inspector determined that according to existing records the electrical isolation between safety systems and downstream equipment not safety-related was completed on May 26, 198 (Closed) Deficiency (285/8620-11): Meteorological Data Not Available In Averaged Form - The NRC inspector toured the Emergency Response Facilities (ERFs) and determined that 17 new 15-minute averaged meteorological data parameters were available in the ERF computer l terminals. Additionally, the NRC inspector reviewed documentation of I

instructions on the use of software change (0 pen) Deficiency (285/8620-13): Inadequacy In Dose Assessment Model -The NRC inspector noted that, according to existing documentation, the EAGLE t

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computer program verification was completed on July 7, 1987. However, the NRC inspector noted that the licensee expects to complete other aspects of this item by June 198 (Closed) Deficiency (285/8620-15): Inadequate Dose Assessment Procedure -

The NRC inspector noted that a new procedure, " Imminent / projected release calculations," was issued to provide instructions and calculations necessary to determine projected whole body and thyroid doses from an imminent or projected release of radioactive effluents from containmen (Closed) Deficiency (285/8620-18): System Availability Calculations lacking - The NRC inspector noted that calculations to determine the percentage of computer systems unavailability-were made for the period July 1 through September 30, 1987, and that the licensee estimated that computer systems were available for over 99 percent of the tim (Closed) Deficiency (285/8620-20): Delay In The Activation Of The Operational Support Center (OSC) - The NRC inspector reviewed documentation and noted that Table B-1 of OPPD's Radiological Emergency <

Response Plan (RERP) was revised.to delineate 11' persons, by position, who will be required to augment the operating shift. These constitute the minimum staffing of the OSC. Procedure EPIP-0SC-2, " Emergency Plan Activation and Notifications," was revised to reflect these changes. In j addition, the NRC inspector noted that the adequacy of staff augmentation was demonstrated during the annual exercis . Program Areas Inspected Emergency Detection and Classification 82201 The NRC inspector held interviews with two Shift Supervisors (SSs) who will act as Site Directors during an emergency, two Shift Technical ;

Assistants (STAS), and two Shift Chemists who would be in charge of making dose assessment calculations. The NRC inspector determined that the SSs understood their authorities and responsibilities to classify events and to make timely protective action recommendations. In addition, the NRC

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inspector noted that the SSs understood the relationships between post-TMI core damage indicators and core statu Protective Action Decisionmaking 82202 During the interviews mentioned above, the NRC inspector determined that i SSs understand which agencies, individuals, and methods of contact are I used to make protective action recommendations (PARS). The NRC inspector also determined that they understood the limitations of their authority and the scope of their reroonsibilities. The NRC inspector noted that the persons interviewed were ware of the need to make immediate protective. " l action recommendations when a general emergency classification was made, i l

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Notifications and Communications 82203 Based on the above interviews and a review of licensee's procedures, the NRC inspector determined that notification procedures were properly l understood, i Shift Staffing and Augmentation 82205 The NRC inspector verified that: a new method for simultaneous paging of ,

the augmentation staff was in place, persons interviewed were familiar

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with the new procedures, and records indicated that during the 1987 exercise the TSC and EOF staffs were in place in a timely manner. The NRC inspector also noted that the augmentation staff was rearranged in order to take residence locations into accoun . Exit Interview The NRC inspectors met with the NRC resident inspector and licensee l representatives denoted in paragraph 1 on November 19, 1987, and sungnarized the scope and findings of the inspection as presented in this report.

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