IR 05000341/1991014

Safety Insp Rept 50-341/91-14 on 910624-28.No Violations Noted.Major Areas inspected:post-accident Monitoring Instrumentation

ML20217D213
Person / Time
Site:	Fermi
Issue date:	07/15/1991
From:	Hausman G, Kopp M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20217D210	List: IR 05000341/1991014 ML20217D208
References
50-341-91-14, NUDOCS 9107220094
Download: ML20217D213 (5)

Text

_ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _

• 1

,

U.S. NUCLEAR REGULATORY COMMISSION REGION Ill Report No. 50 341/91014(DRS)

Docket No. 50-341 License No. NPF-43 Licensee: The Detroit Edison Company 6400 North Dixie Highway Newport, HI 48166 facility Name: Enrico Fermi Atomic Power Plant, Unit 2 Inspection At: Enrico Fermi Site, Newport, MI 48166 Inspection Conducted: June 24-28, 1991 Inspectors: M M. J fopp Mf/>' Date

'

,

44 h,-,. _7f/r/y/

G. M. Hausman Dite '

Also participating in the inspection and contributing to the report was:

A. E. Nolan, EG&G Idaho, In Approved By: k* 6[,lsi i P ! S' 'll F.J(J4bJonski, Chief Date Maintendnce and Outage Section inspection Summary Inspection on June 24-28. 1991 (Report No. 50-341/910141DRS))

Areas inspected: Special announced safety inspection of the licensee's implementation of post-accident monitoring instrumentation in accordance with Regulatory Guide (RG) 1.97, Revision 2 (Module 2515/087);

SIMS Number 67.3.3 (0 pen)

-Results:

o The licensee had implemented a program to comply with RG 1.9 However, one unresolved-item, as discussed in paragraph 3.3, remains open pending furtner NRC review.

j o Closed previously identified unresolved item 341/89008-05(DRP).

i o No violations were identifie M3OoN Q

b

, -

- , . - - - - . _ _ . . . - . -

- _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ - _ _ _ _ _

.

l DETAIL . Principal Persons Contacted The Detroit Edison Compa01

• W. Orser, Senior Vice President

• K. Amin, Senior Engineer Instrumentation and Control

• 5. Catola, Vice President Nuclear Engineering and Services P. Fessler, Superintendent Technical Engineering

• L. Goodman, Director Nuclear Licensing

• R. Newkirk, General Director Regulatory Affairs

• L. Schuerman, General Supervisor Nuclear Engineering

• B. Siemasz, Compliance Engineer

• R. Statford, General Director Nuclear Assurance

• J. Wald Jr., Supervisor Quality Engineering S.' Nuclear Reaulatory Commission B. Drouin, Project Engineer Region III

• S. Stasek, Senior Resident inspector

• Denotes those participating in the site exit on June 28, 199 Other persons were contacted as a matter of course during the inspectio . Licensee's Actions Reaardina.Previously Identified NRC Findinas (Closed) Unresolved Item (341/89008-05(DRP)):

This item was about the circuits for primary containment isolation valve position indication not meeting RG 1.97, Revision 2, Category (Cat.) 1  ;

-requirement l Subsequent to this NRC concern, the licensee initiated Engineering Design Package (EDP) 10610-and Preliminary Design Change (PDC) 11492 to install

. safety related circuits which meet the RG 1.97 Cat. 1 requirement EDP 10610 has been completed and PDC 11492 is scheduled for completion during Refueling Outage 4 (RF04). This item is close . 100en) Temocrary Instruction (TI 2515/087) (SIMS No. 67.3.3)

The inspectors compared the installed RG 1.97 instrumentation to the commitments made in licensee correspondence related to post-accident instrumentation as oescribed in the Detroit Edison Company (DECO) Fermi-2 RG 1.97 Safety Evaluation Report (SER). References used in the assessment were:

RG 1.97, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and following an Accident,"

Revision 2, dated Decerrber 198 . _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -

!

'

.  !

letter RC-LG 85-0050 DECO to NRC, dated September 30, 198 Letter, NRC to Deco, dated September 1,1987, with Technical Evaluation Report prepared for the NRC by EG&G Idaho inc., *Conformance to Regulatory Guide 1.97: Fermi-2," EGG-NTA 7763, dated July 198 '

Letter NRC 89-0201, Deco to NRC, dated September 12, 198 Technical Evaluation Report prepared for the NRC by EG&G idaho inc.,

"Conformance to Regulatory Guide 1.97: Fermi-2," EGG-NTA-7763, dated November 198 SER, NRC to Deco, dated May 2, 199 Letter NRC-90-0095, Deco to NRC, dated June 6, 199 .1 Technical Evaluation of RG 1.97 Instrumentation The inspectors examined the following RG 1.97 variables:

Containment and Drywell Hydrogen Concentration, Cat. 1. Type Containment and Drywell Oxygen Concentration, Cat. 1 Type Cooling Water Temperature to Engineered Safety feature (ESF) System Components, Cat. 2 Type Drywell Pressure, Cat.1. Type Drywell Temperature, Cat. 2, Type LPCI System flow, Category 2, Type Primary Containment Area Radiation - High Range, Cat. 1, Type Reactor Pressure, Cat. 1, Type Reactor Water level (Fuel Zone & Wide Range), Cat. 1, Type RHR Heat Exchanger Outlet: Temperature, Category 2, Type Standby Liquid Control System Storage Tank Level, Cat. 2, Type Status of Standby Power, Cat. 2, Type Suppression Pool Water Level, Cat. 1, Type Suppression Pool Water Temperature, ':at.1, Type The inspectors reviewed the status of SER exceptions, environmental equipment qualification, redundancy, physical and electrical separation, power sources, instrument range, equipment identification, equipment calibration, and system interfaces for the above variables' instrumentation. The inspectors also interviewed plant personnel and inspected the RG 1.97 instrumentation in the control room to assess the implementation of the requirements delineated in RG 1.9 The inspr Mrs determined that there was one RG 1.97 concern as discussed in paragraph 3. The inspectors also discussed the inspection results with the Instrumentation.and Controls Systems Branch (5108) at NRR. Based on the above, the inspectors concluded that the licensee had implemented a program to meet the requirements of RG 1.97, Revision . - .

-.

. _ _ _ _ . __ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ . . _ _ _ _ _ _ _ _

. Status of SER Exceptions 3.2.1 Neutron flux This exception requires the upgrade of the neutron flux monitoring instrumentation to comply with Cat. I requirements of RG 1.97. DECO is participating in the Boiling Water Reactor Owner's Group (BWROG) activities on the wide range neutron monitoring instrumentation. Resolution of this issue is pending NRC actio .2.2 Coolant Level in the Reactor This exception requires the upgrade of the fuel zone instrumentation to comply with Cat. I requirements of RG 1.97. The licensee stated in NRC-90 0095 dated June 6, 1990, that the fuel zone level indicator B21R610, associated cables and power supply will be upgraded to meet the Cat. I requirements of RG 1.9 This modification will be implemented no later than Rf04 per EDP 1149 .2.3 Primary Containment Isolation Valve Position See discussion in paragraph 2.1, 3.2.4 Containment and Drywell Hydrogen /0xygen Concentration This exception concerned the use of non-Class lE power to the recnrder T50R806A. The licensee stated in NRC-90-0095 dated June 6. 1990, that a Class IE power supply will be provided for the containment and drywell  ;

hydrogen / oxygen concentration recorder to meet the Cat. I requirements of RG 1.97. This modification will be implemented during the third refueling outage (Rf03) per EDP 11491, Control Room Instrumentation Identification RG 1.97 requires that all Cat. I and 2, Type A, B, and C instruments be uniquely identified. During discussions held with the licensee and at the time of the control rcom inspection, the inspectors determined that the RG 1.97 control room instruments were not identified. The licensee stated that an exception had been taken with the unique identification requirement of RG 1.97 based on a human factors review. A review of the licensee's submittals showed that this exception was clearly stated; however, the SER had not specifically approved this departure from the RG, This is an unresolved item pending further NRR/SICB review and no licensee action is required at thi_s time. (50-341/91014-01(DRS)) Licensee Commitment The licensee had classified eleven RG 1.97, Cat I control room recorders as quality classification QA-lH. The licensee assigns this quality classification to components and systems that are non-safety related but are important to safety. The licensee stated that these recorders are treated as safety grado components in all aspects except for the procurement proces The inspectors determined that the licensee's submittals did not identify

}

_ _ _ _ _ _ -____ _____ _____- _ _ _ _ __

l

'

.

these recorders as not meeting Class IE requirements. As a res91t, the licensee committed to request NRR/SICB review and approval in apprJximatel/ 30 day . Unresolved items An unresolved item is a matter about which more information is required in order to ascertain whether it is an acceptable item, an open item, a deviation, or a violation. Unresolved items remaining open during this inspection are discussed in paragraph ExiLintervi The Region 111 inspectors met with the licenses's representatives (denoted in Paragraph 1) during the inspection period and at the conclusion of the inspection on June 2S, 1991, lhe inspectors summarized the scope and results l of the inspection findings. The inspectors discussed the likely content of the inspection report with regard to documents or processes reviewed by the inspectors. The licensee acknowledged the information and did not indicate that any of the information disclosed during the inspection could be considered proprietary in natur _

, - _ - -. - . _ .