ML20215C847
| ML20215C847 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 09/29/1986 |
| From: | Andrews R OMAHA PUBLIC POWER DISTRICT |
| To: | Thadani A Office of Nuclear Reactor Regulation |
| References | |
| LIC-86-464, TAC-63047, NUDOCS 8610100484 | |
| Download: ML20215C847 (3) | |
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Omaha Public Power District 1623 Harney Omaha. Nebraska 68102-2247 402/536 4000 September 29, 1986 LIC-86-464 Ashok C. Thadani, Project Director PWR Project Directorate #8 Division of PWR Licensing-B Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington D. C.
20555
References:
1.
Docket No. 50-285.
2.
Letter OPPD (W. C. Jones) to NRC (R. A. Clark) dated April 15, 1983 (LIC-83-093).
3.
Letter OPPD (W. C. Jones) to NRC (J. R. Miller) dated October 28, 1983 (LIC-83-276).
4.
Letter NRC (E. J. Butcher) to OPPD (R. L. Andrews) dated June 7, 1985.
5.
Letter OPPD (R. L. Andrews) to NRC (F. J. Miraglia, Jr.)
dated January 7, 1986 (LIC-86-001).
6.
Letter NRC (F. J. Miraglia, Jr.) to 0 PPD (R. L. Andrews) dated January 9, 1986.
7.
Letter 0 PPD (R. L. Andrews) to NRC (A. C. Thadani) dated April 30, 1986 (LIC-86-195).
Dear Mr. Thadani:
Request for Change of Safety Parameter Display System Variable List As documented in Reference 7, the Omaha Public Power District implemented the Fort Calhoun Station Safety Parameter Display System (SPDS) on April 30, 1986 in accordance with the requirements of Reference 6.
To fulfill the functional requirement of maintaining a one-to-one correspondence between the Emergency Operating Procedure (E0P) Safety Function Status Checks (SFSC) and the SPDS variables, as documented in Reference 5, it was necessary to change (refine) and regroup the Reference 3 variable list.
Both References 2 and 3 identified that the SPDS variable list was being
)
initially developed through the use of the Combustion Engineering Emer-gency Procedures Guidelines (EPGs), because the plant specific E0P upgrade had not yet occurred.
Therefore, changes to the Reference 3 list were anticipated as a result of the upgrade. Additionally, the Fort Calhoun j
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Mr. A. C. Thadani LIC-86-464 Page 2 Station E0P's were developed using the most current revision of the EPG's (Rev. 02) rather than the earlier revision used to generate the Reference 3 list. Completion and implementation of the Fort Calhoun Station E0P's occurred in January 1986 followed by reevaluation and revision of the SPDS.
The purpose of this letter is to request changes to the Reference 3 SPDS list, as approved in the Reference 4 NRC Safety Evaluation, in order to i
resolve discrepancies with the upgraded E0P's and available plant instru-mentation. The requested changes are summarized below:
i 1.
Reauested Chanae:
Replace " Boron-Concentration" with " Emergency Boration".
Discussion:
Both tha EPG's (CEN-152, Rev. 02) and the Fort Calhoun Station E0P's check for boration in-progress if the reactivity control safety function'is not being fulfilled by CEA insertion.
" Emergency Boration" is currently an SPDS variable which checks for the boric i
acid gravity-feed line valves (HCV-258 or HCV-265) being open and at least one charging pump in operation. The " Emergency Boration" para-meter better fulfills the E0P safety function require. ment, because borenometer boron concentration does not directly indicate to the operator if boration is occurring, i.e. increasing boron concentration must be observed.
In addition, should a Safety Injection or Contain-ment Isolation Actuation Signal occur, the boronometer is isolated and misleading information would be provided.
2.
Reauested Chanae: Delete "RCS Average Temperature (T-AVG)"
Discussion:
" Average RCS Temperature" is not a parameter used in plant operations at Fort Calhoun Station. The core inlet and outlet temperatures (T-c and T-h) are utilized and are also available from the SPDS. The E0P's require examination of T-c and T-h rather than "T-AVG".
"T-AVG" can be utilized to indirectly provide secondary system ~ pressure, however, this pressure is directly monitored in the E0P SFSC and the SPDS. Good human factors engineered SPDS displays will prevent the operator from examining or searching through displays containing unessential data in order to evaluate that which is essen-tial. Thus it is concluded that "T-AVG" should be deleted from the parameter list for Fort Calhoun Station.
3.
Reouested Chanae: Delete " Containment Temperature" until an environ-mentally qualified " Representative Containment Temperature" is available, i
Discussion:
Reference to " Containment Temperature" in the EPG's is i
based on a " Representative Containment Temperature" obtainable through multiple sensors located in various containment locations and eleva-tions. Because Fort Calhoun Station has four unqualified RTD's located at only one elevation on HVAC intakes and does not have envir-l onmentally qualified instrumentation located in multiple locations and elevations, a " Representative Containment Temperature" does not exist i
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O Mr.-A. C. Thadani LIC-86-464 Page 3 for utilization with the EPG's (E0P's). Because of the lack of this instrumentation, it was necessary to delete this variable from the E0P's and SPDS and rely on confirmatory indications; if desired the current
" containment temperature" is available for display on the ERF Computer System on which the SPDS resides. Omaha Public Power District is cur-rently studying the feasibility of installing qualified RTD's at various containment locations and elevations during the 1987 refueling outage provided that engineering, design and material procurement can be com-pleted. Upon completion of the aforementioned, both E0P end SPDS changes will be made to include the " Representative Containment Temperature".
Your approval of the above changes is requested. A $150 application fee for this request is enclosed.
If you have any additional questions corcerning this matter, please contact us.
Sincerely,
?? J R. L. Andrews Division Manager Nuclear Productions RLA/KCH/bjb Enclosure pc:
LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.
Washington, D.C.
20036 Mr. D. E. Sells, NRC Project Manager Mr. P. H. Harrell, NRC Senior Resident Inspector
.e I
.