ML20138E108

Requests Addl Info within 60 Days to Complete Review of 850228 Submittal Re Conformance of Accident Monitoring Instrumentation to Provisions of Reg Guide 1.97,Rev 2. Interim Safety Evaluation Encl

ML20138E108
Person / Time
Site:	Grand Gulf
Issue date:	12/06/1985
From:	Butler W Office of Nuclear Reactor Regulation
To:	Richard J MISSISSIPPI POWER & LIGHT CO.
Shared Package
ML20138E112	List: ML20138E108 ML20138H132
References
RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097, TASK-2.B.3, TASK-TM TAC-51094, NUDOCS 8512130342
Download: ML20138E108 (2)

Text

. *

. December 6,1985 Docket No.: 50-416

-Mr. Jackson B. Richard Senior Vice President, Nuclear Mississippi Power and Light Company

P.O. Box 23054 Jackson, Mississippi 39205

Subject:

Grand Gulf Unit 1 - Accident Monitoring Instrumentation (Regulatory Guide 1.97)

By letter dated February 28, 1985, Mississippi Power and Light Company discussed the confontance of the accident monitoring instrumentation in Grand Gulf, Unit 1 to the provisions of Regulatory Guide 1.97, Revision 2,

" Instrumentation for Light-Water-Cooled Nuclear Power '" ants to Assess Plant and Environs Conditions During and Following an Accident." Conformance to Regulatory Guide 1.97 is required by Generic Letter 82-33 (NUREG-0737, Supplement 1) and Grand Gulf License Condition 2.C.(36). License Condition 2.C.(36) requires that all instrumentation except flux monitoring, coolant level monitoring, and star.dby liquid control systera (SLCS) flow monitoring meet the provisions of Regulatory Guide 1.97 prior to startup following the first refueling outage. The flux monitoring, coolant level monitoring and SLCS flow monitoring instruments are required to conform to Regulatory Guide 1.97 prior to startup following the second refueling outage.

The NRC staff has reviewed the February 28, 1985, submittal and finds that additional information is needed to complete its review of the conformance of Grand Gulf Unit 1 to Regulatory Guide 1.97. The staff's interim safety evaluation report, prepared by its consultant EG&G Idaho, Inc., is enclosed.

The staff finds that the February 28, 1985, subraittal provides adequately explicit descriptions of certain instrumentation that presently complies with Regulatory Guide 1.97, and of commitments to modify certain instruments to meet the provisions of Regulatory Guide 1.97. However, some of the proposed deviations of certain instrumentation frcm the provisions of Regulatory Guide 1.97 are not adequately justified. Instrumentation for which deviations are not adequately justified is identified in Section 4 and discussed in Section 3 of the enclosed interim safety evaluation.

Sections 3.3.1 " Reactor Coolant System Soluble Baron Concentration," 3.3.5

" Radiation Level in Circulating Primary Coolant," and 3.3.21 " Accident Sarrpling" of the enclosed safety evaluation state that the instrumentation and sampling described in these sections is addressed by the NRC in its review of NUREG-0737, Iten II.B.3 " Post Accident Sampling." In Supplement 5 to the Safety Evaluation Report (h0 REG-0831), the staff concluded that the licensee 0512130342 851206 7 PDR ADOCK 05000416 F PDR s

, has complied with the criteria of Item II.B.3, exccpt for the procedure to estinate core damage based on radionuclide gaseous and ionic species.

Therefore, the instrumentation and sampling capabilities described in Sections 3.3.1, 3.3.5, and 3.3.21 of the enclosed safety evaluation are acceptable.

The precedure for estimating post accident core damage is required by License Condition 2.C.(33)(c) and will be addressed separately.

In order to complete our review of the conformance of Grand Gulf Unit I accident trenitoring instrumentatien to Regulatory Guide 1.97, we require additional information identified in Section 4 of the enclosed safety evaluation. Items 2, 3,and 4 state that the environmental qualificaticr. cf instrumentation for the core spray system flew, standby liquid control system storage tank level, and cooling water flow to engineered safety feature system components sheuld te addressed in accordance with 10 CFR 50.49. For these three items, provide justification for any prcpcsed exerrptions from the requirements of 10 CFR 50.49. In accordance with Licence Ccndition 2.C.(36), the provisions of Regulatory Guide 1.97 for these three items including approved exemptions, if justified must be iraplemented prior to startup follwing the first refueling cutage.

In order to meet the schedule for ccmpletion of our review, you are requested to submit this additional information within 60 days of the receipt of this letter.

If you cannot teet this date, please advise the NRC Project Panager, L. L. Kintner.

The reporting and/or recordkeeping requirenents contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.

Sincerely,

. Original Signed by Walter R. Butler, Director BWR Project Directorate No. 4 Division of EUR Licensing

Enclosure:

As stated cc w/enclcsure:

See next page

• Pr 9 usly concurred DL:S.5s4 DL:LB#4 EQB CHEB ICSB DL:LB#4 LKint er:nn *f:Duncan

• RLaGrange

• FWitt *JJoyce

• EAdensam 11/ /85 11/07/85 11/08/85 11/08/85 11/12/85 t1/14/05 1-0:BKF04 r I WRButler j 11/d,/85 4