ML20210C542

Forwards Responses to Staff Questions Re SPDS & Request for Addl Info on Reg Guide 1.97 Concerning Reactor Bldg Temp,Per 870330 Commitment

ML20210C542
Person / Time
Site:	Rancho Seco
Issue date:	04/30/1987
From:	Julie Ward SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Miraglia F Office of Nuclear Reactor Regulation
References
RTR-REGGD-01.097, RTR-REGGD-1.097 JEW-87-760, NUDOCS 8705060221
Download: ML20210C542 (16)

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esuun SACRAMENTO MUNICIPAL UTILITY DISTRICT El P. O. Box 15830 Sacramento CA 95052 1830,(910) 452 3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CAllFORNIA APR 3 01997 JEW 87-760 Director of Nuclear Reactor Regulation Attention: Frank J. Miraglia, Jr.

Division of PWR Licensing-B l

U S Nuclear Regulatory Commission Washington D C 20555 Docket 50-312 Rancho Seco Nuclear Generating Station Unit #1 SPDS/ REGULATORY GUIDE 1.97 RESPONSE TO NRC QUESTIONS Reference Letter from J. E. Ward to F. J. Miraglia, Jr., CRDR/SPDS Response to NRC Requests, dated March 30, 1987 1

Dear Mr. Miraglia In the referenced letter, the District committed to provide responses to several items. Attachment 1 contains the responses to the staff's questions on SPDS. The staff has also requested additional information with regards to the Regulatory cuide 1.97 reactor building temperature monitor. Attachment 3 provides the information requested.

l If you have any questions', please contact John Atwell of my staff.

Sincerely,

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Jo ard l

Deputy General Manager, Nuclear Attachments I

cc George Kalman, NRC - Bethesda A. D'Angelo, NRC - Rancho Seco l

l 8705060221 87043o fDR ADOCK 0500031g

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PDR DISTRICT HEADQUARTERS L10201 S Street, Sacramomo CA 05017 1899

ATTACHMENT 1 Response to NRC Requests for Information Request:

Commitment to perform a task analysis of Emergency Operating i

Procedures, Cautions, Notes, and Status tasks along with new l

operator tasks identified as a result of the Emergency Operation Procedures rewrite project.

Responset The task analysis of the revised Emergency Operating Procedures has been completed. Evaluations are underwayt To compare the control requirements from the task analysis with the Control Room inventory.

• To assess the Human Engineering Observations identified during the above task analysis.

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Request:

Commitment to perform a task analysis of Hydrogen Purge Procedure A.52.

t Responso: The task analysis of A.52 has been completed.

Request:

The staff requested that a copy of the final design of the alphanumeric display formats be included in the revised SPDS SAR.

Responset As committed in the District's March 30, 1987 submittal, Attachment l

2 contains pictures of each display screen.

l Request:

The licensee should discuss how configuration control for both hardware and software will be achieved and how modifications will be qualified and tested.

Responset The configuration control program for both the hardware and software is provided as described in the District's November 20, 1986 submittal (item 4.6.a.3.0).

The current modifications are being reviewed by B&W as part of their validation and verification program prior to installation. A detailed acceptance test will be performed on the SPDS prior to restart using the District's Special Test Procedure (STP) 789.

All future modifications will be qualified and tested in a manner commensurate with the methods used in qualifying and testing the original components.

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ATTACHMENT 1 (Cont.)

Response to NRC Requests for Information l

Request:

Provide the documents and data that illustrato that the upgraded SPDS complies with industry and regulatory criteria and standards for safety-related systems (i.e., IEEE Std. 323, 1974, Standard for Qualification of Class 1E Equipment for Nuclear Power Generating Stations, IEEE Std. 344-1975, Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power, etc.), per RG 1.97.

Responset Tha SPDS has been designed to meet the qualification requirements i

for Category 1 variables per Regulatory Guide 1.97 (i.e.

environmental and seismic qualification from the sensor up to and including the SPDS). Those sensors not located in a mild environment have been qualified to the requirements of IEEE 323-1974 and 344-1975.

The Class 1 SPDS components which are located in a mild environment are che multiplorer units (No.'s 1, 3, 5, 7, & 9), the CSU & CCU's 1 & 2 and the SPDS computer, control panel and CRT display. These components do not require environmental qualification due to their location. However, Seismic qualification is required for each of these items. Due to modifications of the components, the seismic qualification documentation is not presently available. When modifications are complete, documentation will be available showing seismic qualification of these items.

Request:

The staff expects the District to docket (send to the NRC) the functional specification for the upgraded SPDS for a detailed review.

Responset A copy of the SPDS functional description will be available upon incorporation of the District's comments. Revision of the specification and submittal to the staff is expected to occur in May.

Request:

At the April 7,1987 meeting a question was asked about the fire wrap discussed in item 4.6.a.6.0 of the District's November 20, 1987 submittal.

Responset As a result of the review by the Appendix "R" group, there were no instances requiring fire wrap of any SPDS cable.

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ATTACHMENT 3 Additional NRC Question Regulatory Guide 1.97 Question: The staff's reviewer for Regulatory Guide'1.97 has asked whether or not the Reactor Building (10B)-temperature could be found in any of the Emergency Operating Procedures (EOP).

Response:.The E0P's have been reviewed and only one reference to the RB

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temperature monitor is made. ~This is found in Cooldown Procedure CP101~and reads as follows:

Jg[ any of the following occur THEN Start 4 RB coolers with maximum NSCW and NSRW.

-.1 RB pressurefis greater than or equal to 4'psig.

.2 RB temperature is greater than or equal to.high temperature limit (1200F), or RB temperature indication is lost.

.3 RB radiation is greater than'the high radiation limit.

.4 RB H2 concentration is greater than or equal to 3.5 percent.

As noted above, if the RB temperature is not available, the procedure requires the coolers be started.. Thus,.the. procedure will cause the operator to perform the safety action with. loss of indication. As documented in the District's March 30, 1987 submittal (Attachment 4) RB pressure, hydrogen concentration and containment radiation are the key' Category 1 variables. for' controlling the containment building, environment. -Each of these

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variables are included in this procedural step -thus providing the operator sufficient indication for action.

Based on the three key ~ variables being listed in.the procedure and the RB temperature indication loss. causing the oper.stor to perform I

the safety action,'the District l considers the position for a

.l Category 3 RB temperature monitor to be acceptable.

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