ML20116J452

Safety Evaluation Supporting Amends 114 & 112 to Licenses DPR-80 & DPR-82,respectively

ML20116J452
Person / Time
Site:	Diablo Canyon
Issue date:	08/01/1996
From:	NRC (Affiliation Not Assigned)
To:
Shared Package
ML20116J447	List: ML20116J446 ML20116J452
References
NUDOCS 9608130213
Download: ML20116J452 (3)

Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASH 0NGTON, D.C. 20665-0001 o

g SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 114 TO FACILITY OPERATING LICENSE NO. DPR-80 AND AMENDMENT NO. 112 TO FACILITY OPERATING LICENSE NO. DPR-82 PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT. UNITS 1 AND 2 QDCKET NOS. 50-275 AND 50-323

1.0 INTRODUCTION

By application dated May 9,1996, Pacific Gas and Electric Company (or the licensee) requested changes to the Technical Specifications (Appendix A to Facility Operating License Nos. DPR-80 and DPR-82) for the Diablo Canyon Nuclear Power Plant, Units 1 and 2.

The proposed changes revise the combined Technical Specifications (TS) for the Diablo Canyon Nuclear Power Plant (DCPP), Unit Nos. I and 2 to revise Technical Specifications (TS) 3/4.3.2,

" Engineered Safety Features Actuation System Instrumentation," and 3/4.6.2,

" Containment Spray System." The changes clarify the description of the initiation signal required for operation of the containment spray (CS) system at DCPP and correctly incorporate changes made in previous license amendments (LAs). All of the changes are administrative in nature.

2.0 EVALUATION 2.1 Containment Soray The licensee proposed to change TS Tables 3.3-3, 3.3-4, and 4.3-2 to provide uniformity across the instrumentation TS regarding CS initiation.

TS 3.3.2, Table 3.3-5, " Engineered Safety Features Response Times," Initiating Signal and Function 1.b.1), already lists the spray initiating signal as " Containment Spray (Coincident with SI Signal)." Table 3.3-5 was reviewed and approved as an administrative change as documented in the original Unit I and 2 Combined TS, issued as NUREG-ll51 in August 1985.

The change to TS 4.6.2.1.c.1) and 2) revises the TS from verification of CS pump ar.d valve actuation on "a Phase B Isalation test" signal to verification on "an actual or simulated actuation" signal. This wording envelopes the interlocking SI signal which was previously understood to be part of the Phase B test signal. The proposed signal descriptions conform to NUREG-1431, Rev. 1, TS 3.6.6A, " Containment Spray and Cooling Systems (Atmospheric and Dual)," Surveillance Requirements (SRs) 3.6.6A5 and 3.6.6A.6.

9608130213 960801

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PDR ADOCK 05000275 P

PDR

. Containment Phase B isolation signals are generated for two purposes: CS initiation and essential process line isolation. Automatic Phase B isolation signals are generated when two out of four containment pressure channels exceed 22 psig. Manual Phase B signals are generated by actuating two control board switches simultaneously. The SI signal on containment high pressure is generated when two-out-of-three containment pressure channels exceed 3 psig.

Containment spray pumps start and automatic discharge valves open upon receipt of a phase B isolation signal only when a coincident SI signal is present.

The SI signal functions to initiate the automatic timers for all of the engineered safety feature (ESF) pumps, including the CS pumps. The interlocking SI signal is required for either automatic or manual actuation of the CS system. The required interlock is generated by any manual or automatic SI actuation.

The interlock signal is physically provided by solid state protection system slave relays which actuate on a SI signal. No SI interlock is required for essential process line (Phase B) isolation to occur. An interlocking SI signal is not required to initiate spray using the individual pump and valve control switches located in the control room. The interlock is used to ensure the CS pumps will load onto the vital 4kV busses in the proper sequence with other ESF pumps. A secondary function is to prevent personnel from inadvertently spraying the containment during testing.

The staff has evaluated this change and concludes that these changes are administrative and are therefore acceptable.

2.2 Administrative Corrections to Table 4.3-2 The proposed administrative revisions to TS Table 4.3-2, pages 3/4 3-32, 3/4 3-34, and 3/4 3-35 correct the headings that were inadvertently revised in various LAs. Also, on page 3/4 3-32, a notation is restored defining the frequency for specific slave relay tests.

For TS page 3/4 3-32, changes made in LA 84/83 to have the fourth and fifth column headings read " CHANNEL OPERATIONAL TEST" and " TRIP ACTUATING DEVICE OPERATIONAL TEST," respectively, and in LA 87/86 to add notation "(4)" to Functional Unit 1.b were inadvertently revised in LA 89/88 issued on March 2, 1994.

For pages 3/4 3-34 and 3/4 3-35, changes made in LA 84/83 to have the fourth and fifth column headings read " CHANNEL OPERATIONAL TEST" and " TRIP ACTUATING DEVICE OPERATIONAL TEST," respectively, were inadvertently revised in LA 103/102 issued on June 2, 1995.

The staff has evaluated this change and concludes that these changes are administrative and are therefore acceptable.

3.0 STATE CONSULTATION

In accordance with the Commission's regulations, the California State official was notified of the proposed issuance of the amendments.

The State official had no comments.

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. 4.0 ~ ENVIR0felENTAL CONSIDERATION These amendments change a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and change surveillance requirements. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (61 FR 31184). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).

Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

5.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor:

S. Bloom Date:

August 1,1996 1

August i, 1996 Mr. Gregory M. Rueger.

Pacific Gas and Electric Company NPG - Mail Code A10D P. O. Box 770000 San Francisco, California 94177

SUBJECT:

ISSUANCE OF AMENDMENTS FOR DIABLO CANYON NUCLEAR POWER PLANT, UNIT NO.1 (TAC NO. M5434) AND UNIT NO. 2 (TAC NO. M95435)

Dear Mr. Rueger:

The Commission'has issued the enclosed Amendment No.114 to Facility Operating License No. DPR-80 and Amendment No.112 to Facility Operating License No.

DPR-82 for the Diablo Canyon Nuclear Power Plant (DCPP), Unit Nos. I and 2, respectively. The amendments consist of changes to the Technical Specifications (TS) in response to your application dated May 9,1996.

These amendments revise the combined Technical Specifications (TS) for the Diablo Canyon Nuclear Power Plant, Unit Nos. I and 2 to revise Technical Specifications (TS) 3/4.3.2, " Engineered Safety Features Actuation System Instrumentation," and 3/4.6.2, " Containment Spray System." The changes clarify the description of the initiation signal required for operation of the containment spray system at DCPP and correctly incorporate changes made in previous license amendments. All of the changes are administrative in nature.

A copy of the related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Ccmmission's next regular biweekly Federal Reaister

notice, i

Sincerely, Original Signed By l

Steven D. Bloom, Project Manager

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Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-275 DISTRIBUTION and 50-323 Docket File CGrimes, 011E22 PUBLIC JBianchi, WCF0 (2)

Enclosures:

1.

Amendment No.114 to DPR-80 PDIV-2 Reading GHill (4), T5C3 2.

Amendment No.112 to DPR-82 EPeyton OGC, 015818 1

3.

Safety Evaluation LHurley, RIV ACRS, T2E26 WBateman DChamberlain, RIV cc w/encls:

See next page KPerkins, WCF0 CVM (SE)

SBloom JDyer, RIV JKilcrease, WCF0 TMarsh DOCUMENT NAME:

DC95434.AMD OFC LA:PDIV-2 PDIVp2 HIQS.

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OGC PDIV-2

,i NAME EN SB[ok JWeh b D W/ WBate M D DATE 7/8/96 7k/96-7/f/96 7/p/96 7/8//96 0FFICIAL RECORD COPY