ML20213F700

Forwards Request for Addl Info Re Sys Review & Test Program. Questions Include Sys & Components Controlled in Tech Specs, Including Containment Isolation Valves,Core Flood Tanks & Pressure Boundary Isolation Valves

ML20213F700
Person / Time
Site:	Rancho Seco
Issue date:	11/06/1986
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Julie Ward SACRAMENTO MUNICIPAL UTILITY DISTRICT
References
TAC-62083, NUDOCS 8611170033
Download: ML20213F700 (3)

Text

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I November 6,1986 Docket No. 50--312 O

Mr. John E. Ward

. Sacramento Municipal Utility District Rancho Seco Nuclear Generating Station

Post Office Box 15830, Mail Stop No. 291 Sacramento, California 95852-1830

SUBJECT:

RANCHO SEC0 NUCLEAR GENERATING STATION - REQUEST FOR ADDITIONAL INFORMATION Our contractor, Idaho National Engineering Laboratory (INEL), has completed i its initial review of the list of selected systems as part of the Rancho Seco SRTP review. The review was based on systems which are assumed to operate in the Rancho Seco Accident Analysis (USAR Chapter 14, Amendment 4), and systems and components included in the Technical Specifications (Revision 73).

As a result of their review, the enclosed list of questions was developed.

Please note that the-questions include systems and components controlled in the Technical Specifications. Some of these components, such as containment isolation valves, core flood tanks, pressure boundary isolation valves, etc.,

may Tlready be included in the SRTP for other selected systems. Some of the systems may not be required to be included in the SRTP if adequate justification is provided. Within 7 days of receipt of this letter, please provide a schedule for responding to this request for additional information..

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

Sincerely, l

!1 John F. St lz, Director PWR Project Directorate #6 Division of PWR Licensing-B l

Enclosure:

Request for Additional Information cc w/ enclosure

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Mr. John E. Ward Rancho Seco Nuclear Generating Sacramento Municipal Utility District Station cc:

Mr. David S. Kaplan, Secretary Sacramento County and General Counsel Board of Supervisors Sacramento Municipal Utility 827 7th Street, Room 424 District Sacramento, California 95814 6201 S Street P. O. Box 15830 Ms. Helen Hubbard Sacramento, California 95813 P. O. Box 63 Sunol, California 94586 Thomas A. Baxter, Esq.

Shaw, Pittman, Potts & Trowbridge 2300 N Street, N.W.

Washingtnn, D.C. 20037 Mr. Ron Columbo Sacramento Municipal Utility District Rancho Seco Nuclear Generating Station 4440 Twin Cities Road Herald, California 95638-9799 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 Resident Inspecto'r/ Rancho Seco c/o U. S. N. R. C.

14410 Twin Cities Road Herald, California 95638 Regional Administrator, Region V U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Director Energy Facilities Siting Division Energy Resources Conservation &

Development Commission 1516 - 9th Street

' Sacramento, California 95814 Mr. Joseph 0. Ward, Chief Radiological Pealth Branch State Department of Health Services 714 P Street, Office Building #8 Sacramento, California 95814

I I

Enclosure Request for Additional Information Rancho Seco Nuclear Generating Station Docket No. 50-312 Rancho Seco System Review And Test Program The review of systems included in the Rancho Seco System Review and Test Program (SRTP) has been completed by the Idaho National Engineering Laboratory.

The following questions have resulted from this review.

1. It is our understanding that once a system is designated as " selected" for inclusion in the SRTP, it cannot be removed or otherwise be deleted from the test program. Is this correct?

2. Are the hydrogen purge system and hydrogen analyzer, which are referenced in the USAR Accident Analysis (pgs. 14.3-14 and 14.3-15), included in the SRTP under some other system?

3. Does the borated water system include the boric acid pumps which are referenced in USAP Chapter 14 (pgs. 14.1-49 and 14.1-34)?

4. The listing of selected systems stated that only the high pressure injection portion of the makeup system is considered safety related. Does this include the dilution valve interlock setpoints referenced on USAR (pgs.14.1-12 and 14.1-13)?

5. USAR Section 14.2.2.2.4 (pg. 14.2-17) discusses the charcoal bed in the plant vent. Is this bed included as a portion of the ventilation systems included as safety related systems?

6. The following components or systems are included in the Rancho Seco Technical Specifications:

a. Reactor building polar crane and auxiliary hoist

b. Snubbers

c. Fire detection systems

d. Fire suppression systems

e. Padioactive liquid waste

f. New and spent fuel storage and facilities

g. Core flood tanks

h. Reactor building emergency cooling system

1. Reactor building spray system J. Condensate storage tank system

k. Pressure boundary isolation valves

1. Control rod drive system

m. Containment isolation valves

n. Diesel fuel oil system

o. Auxiliary building and spent fuel building filter system

p. Radioactive waste effluent monitoring systems

q. Radiological environmental monitoring system

r. Radioactive waste sampling and analysis systems

s. Nuclear service electrical building emergency HVAC system

t. Nuclear instrumentation systems

u. Plant computer system Does the Sacramento Municipal Utility District plan any testing for these components or systems as part of the SRTP?

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