ML20204H268
| ML20204H268 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 07/28/1986 |
| From: | Andrews R OMAHA PUBLIC POWER DISTRICT |
| To: | Thadani A Office of Nuclear Reactor Regulation |
| References | |
| LIC-86-314, NUDOCS 8608080067 | |
| Download: ML20204H268 (3) | |
Text
~
Omaha Public Power District 1623 Harney Omdha Nebraska 68102 2247 402/536 4000 July 28, 1986 LIC-86-314 Mr. 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, DC 20555
References:
(1) Docket No. 50-285 (2)
Letter NRC (J. R. Miller) to OPPD (W. C. Jones) dated July 11, 1984 (3) letter OPPD (R. L. Andrews) to NRC (J. R. Miller) dated August 2, 1984 (LIC-84-250)
(4)
Letter OPPD (R. L. Andrews) to NRC (J. R. Miller) dated September 28, 1984 (LIC-84-323)
(5)
Letter OPPD (R. L. Andrews) to NRC (J. R. Miller) dated March 1, 1985 (LIC
)
(6)
Letter OPPD (
Andrews) to NRC (E. J. Butcher) dated June 27, 1985 LIC-85-211)
(7)
Letter OPPD (R. L. Andrews) to NRC (E. J. Butcher) dated July 19, 1985 (LIC-85-319)
(8)
Letter OPPD (R. L. Andrews) to NRC (A. C. Thadani) dated December 20, 1985 (LIC-85-523)
(9)
Letter OPPD (R. L. Andrews) to NRC (A. C. Thadani) dated March 21, 1986 (LIC-86-076)
Dear Mr. Thadani:
Inadequate Core Cooling Instrumentation (ICCI) System Implementation Letter Report In Reference 2, the NRC requested additional information of OPPD garding the evaluation of OPPD's Inadequate Core Cooling Instrumentation System.
Enclosure 2 of reference 2 requested a milestone schedule for implementation of the ICCI.
Item 6 of these milestones was an Implementation Letter Report to be submitted to the NRC.
This Letter Report was to contain the following:
(1) Notification that the system installation, functional testing, and calibration is complete and test results are available fer inspection.
8608080067 860/?n PDR ADOCK 050006e5 P
P re t-h emouum ng;;ttgt<;ugopportunitu as sie4
Ashok C. Thadani LIC-86-314 Page 2 (2) Summary of licensee conclusions based on test results, e.g.:
(a) the system performs in accordance with design expectations and within design error tolerances; or (b) description of deviations from design performance specifications and basis for concluding that the deviations are acceptable.
(3) Description of any deviations of the as-built system from previous design descriptions with any appropriate explanation.
(4) Request for modification of Technical Specifications to include all ICC instrumentation for accident monitoring.
(5) Request for NRC approval of the plant-specific installation.
-(6) Confirm that the E0P's used for operator training will conform to the technical content of NRC approved Emergency Procedure Guidelines (generic or plant specific).
In Attachment 2 to Reference 4, OPPD provided a milestone date for this imple-mentation letter of "6 months after the 1985 refueling outage."
Reference 8 documented certain difficulties OPPD had experienced with portions of the ICC hardware and requested extension of the ICCI implementation for one full fuel cycle.
In two telephone conversations between OPPD and NRC staff, this extension was discussed. The results of those conversations were documented in Reference 9 and are as follows:
(1) Six months after the 1985 refueling outage, OPPD will submit the implementation report letter in conjunction with an Application for Amendment containing proposed Technical Specifications for the ICCI system.
(2) Based on certain hardware difficulties, and a lack of " operating exper-ience" with the new equipment, the proposed Technical Specifications were discussed with the NRC staff. As agreed to, these specifications will be less restrictive than the Standard Technical Specifications, in lieu of a one-cycle delay.
l (3) Request will be made that those Technical Specifications become effec-tive 150 days from submittal or 60 days from NRC approval, whichever is later.
On April 29, 1986, the Fort Calhoun Station System Acceptance Committee (SAC) accepted modification MR-FC-81-99 " Instrumentation for the Detection of Inade-quate Core Cooling". At that time, it was verified that the Inadequate Core Cooling Instrumentation System installation, functional testing, and calibra-tion was complete.
Based on the test results, OPPD concludes that the system does, in fact, perform in accordance with its design expectations and within design error tolerances.
i Mr. Ashok C. Thadani LIC-86-314 Page 3 In Reference 6, OPPD submitted to the NRC the final design description for the ICCI system. This submittal was subsequently revised per Reference 7.
There are no deviations in the as-built system from these descriptions previously supplied to the NRC.
The Fort Calhoun Station Emergency Operating Procedures are based upon the NRC approved Combustion Engineering Procedure Guidelines and were developed in ac-cordance with the Procedures Generation Package (Reference 5).
In accordance with OPPD procedures, the application for amendment of Operating License, requesting to amend the Technical Specifications for ICCI, are being forwarded to our legal counsel in Washington, D.C.
They will be delivered to the NRC and filed with the Commission in our usual fashion. The letter to the NRC accompanying the Application for Amendment will specify, as noted earlier, that 150 days from date of filing, or 60 days from date of NRC approval is re-quested by 0 PPD for implementation.
Sincerely, h%
R. L. Andrews Division Manager Nuclear Production RLA/DJM:me cc: LeBoeuf, Lamb, Leiby, & MacRae 1333 New Hampshire Ave., N. W.
Washington, DC 20036 D. E. Sells, NRC Project Manager P. H. Harrell, NRC Senior Resident Inspector t
(