ML20198T080
| ML20198T080 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 06/07/1986 |
| From: | Agosti F DETROIT EDISON CO. |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| VP-86-0066, VP-86-66, NUDOCS 8606110290 | |
| Download: ML20198T080 (2) | |
Text
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eP s snt Nuclear Operatgms M
Detroit r.-
Edison 5595258 c.L.
June 7, 1986 VP-86-0066 Director of Reactor Regulation Ms. Elinor G. Adensam, Director Project Directorate No. 3 Division of BWR Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Ms. Adensam:
Reference:
Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43
Subject:
Intent to Request for an Emergency Amendment to the Fermi 2 Technical Specifications Governing Emergency Core Cooling System Actuation Instrumentation Setpoints A recent update of degraded grid relay design calculations indicates that the setpoints for Division I degraded grid relays should be changed to correspond to the minimum degraded grid voltage necessary to protect Class IE equipment.
These setpoints are in Technical Specification 3/4.3.3. The purpose of this memo is to identify Detroit Edi. son's intent to request an emergency Technical Specification change.
Nuclear Engineering identified the potential undervoltage condition on May 27, 1986.
Additional information obtained from equipment vendors confirmed the existence of a discrepancy between the Technical Specification and calculational values and a Deviation / Event Report (DER) was issued on June 4, 1986.
The design calculation is currently in its final approval cycle.
Upon receipt of the DER, the Nuclear Shift Supervisor determined the condition to be reportable in accordance with 10CFR50.72.
On June 4, 1986 at 0815 hours0.00943 days <br />0.226 hours <br />0.00135 weeks <br />3.101075e-4 months <br />, a report was made to the NRC via the emergency notificution system.
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Ms. Elinor G. Adensam June 7, 1986 VP-86-0066 Page 2 Section 3/4.3.3 of the Fermi 2 Technical Specifications require the Emergency Core Cooling System actuation instrumentation channels shown in Table 3.3.3-1 to be operable with their trip setpoints set consistent with the values shown in the trip setpoint column of Table 3.3.3-2.
The updated calculation renders the values of Table 3 1 3-2 part 5.b.a and 5.b.b for Division I incorrtet.
Therefore, the intent of Technical Specification operability has not been met for Division I.
In accordance with Table 3.3.3.-1, item 5.2, the loss of power (degraded voltage) function is required to be operable in Operational Condition 1, 2, 3, 4**,
5**
(**
required when ESF equipment is required to be operable).
The plant is presently in operational Condition 5 with the required onsite AC electrical power source, per Technical Specification 3.8.1.2.b, being supplied by Division II Emergency Diesel Generators (EDG's).
In accordance with our outage schedule, Division I EDGs had previously been placed in an inoperable condition due to outage work.
To complete our outage, Division I is scheduled to become operable on June 13, 1986 so that Division II work may begin.
This Technical Specification change is required to declare Division I operable and allow completion of the remaining outage activities.
Detroit Edison intends to request approval of an emergency Technical Specification change to preclude a restart delay.
Submittal of a complete request for license amendment will be made as soon as possible.
A copy of this letter is being forwarded to the State of Michigan to provide early notice of our intended request.
If further discussion is necessary, please contact Mr.
R. L. Woolley, (313) 586-4211.
Sincerely, n 'h
}J cc:
Mr. M. D. Lynch Resident NRC Inspector l
Supervisor, Advance Planning and Review Section Michigan Public Service Commission USNRC Document Control Desk Washington, D. C.
20555