ML19319C192
| ML19319C192 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/29/1976 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | Knop R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML19319C193 | List: |
| References | |
| NUDOCS 8002050782 | |
| Download: ML19319C192 (2) | |
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R. C. Knop, Chief, Reactor Projects Section
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Karl V. Seyfrit, Chief, Reactor Technical Assistance Cranen. IE SLBJECT:
uAVIS BESSE 1 - RESP 0:4SE TI;fE TESTI:lG AS~4MPTIGtS REGARDInG SAFETY-RELATED CGtP0;aTS Ana SYSTCis - AITT F30230iil i
This ruemorandwa discusses the technical cuicance proviced R.D. :tartin of your office during tne telecen witn R. Warnick (IE:hQ) on Novascr 26, 1976.
The inspector turcugh AITS F00230!il, requested headquarters assistance in the assess.Txnt of the validity of two basic assu:nptions oeing e.nployed of this licensea to cetermine tne response times of safety related cccponents and siystens. First, tne licensee assuces enat sioilar analog devices havo equivalent response time character-istics for increasing and accreasing input signals. Soccnd, tie licensee assaes that for large ;;opulations of identical devices.
(e.g. relays, trans:aitters, amplifiers, RTDs, etc.) the respcase tinas of tnese dovices can ce determined by measuring sample numbers of tha devices. For additional details on these t.o points refer to tne attached memoranda froia R. D. Martin, RIII to R. C. Knap, RIII dated October 5,1976, and frac R. C. Knop to K. V. Seyfrit dated iicycre,er 2,197o.
RTAB has reviewed tha information provided against the related test requirements specified in this facility's FSAR ana Technical Specift-cations; we nave also reviewed sis;1lar rgquirunents in the Standard Technical Specifications. The r.dtter has been discussed with the Tecnnical Specification Group in NRR-D0R.
Ce the basis of these : reviews and the discussions held with HRR-DOR we nave determined that:
1.
The assumption that similar analog devices have equivalent res;;onse time characteristics for increasing and decreasing input signals would 50-3 4 noc fulfill related test requirements imposed by hRR-DOR on licensees
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prior to initial plant start-ua. MRR-COR requires that prior to in mai plant start-up eaca instrument chanrel Lt,ica provides an input
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l 3EC 2u ys actuation signal to either the RPS or ESFAS be tested to detemine overall safety system response time.
Subsequent to. initial plant start-up similar response time test requirerments imposed by DOR are less stringent. Standard Tecnnical Specifications then require that a single instrw.ent channel wnich is representative of any number of mutually reduncant safety-related channels be tested to determine its overall system responsa time curing eacn refueling outage.
In addition, installed safety-related senscrs aay be replaced with identical si. elf units without a response time test provided tr.at che remaining part of the instracnt actuation enannel in unich tne sensor is replaced is tasted to determine over-all syste response tlac.
2.
With regard to the licensee's second assumption, it is our view, that cased on the aboYe findings the sampling Method is also unaC0ept-able for the initial testing of identical safety related davices.
We consider this matter closed and plan no furtner action.
C:::a:>fr.gn)
K.V. seyr:.a Kiri V. Seyfrit, Chief Reactor Technical Assistance Oranch Office of Inspection and Enforcer: ant
Enclosure:
1.
P,ero. R. D. 11artin, RIII to R. C. Knop, RIII, dd. 10/a/76 2.
Memo, R. C. L1cp to K. V. Seyfrit, do.
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