ML20210S931

Forwards Assessment of SER Sections 6.4,9.2.1.2,9.5.4.2,10.2 & 10.4.9 Re Acceptability of plant-specific Tech Specs

ML20210S931
Person / Time
Site:	Beaver Valley
Issue date:	02/10/1987
From:	Rossi C Office of Nuclear Reactor Regulation
To:	Tam P Office of Nuclear Reactor Regulation
References
TAC-62942, NUDOCS 8702170737
Download: ML20210S931 (7)

Text

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~ UNITED STATES

[i9,@. 4*t NUCLEAR REGULATORY COMMISSION f

,$ WASHINGTON, D. C. 20665 A

FEB 101987 NEM0PANDUM FOR: Peter Tam, Project Manager PWR Project Directorate No. 2 Division of PWR Licensing - A FROM: Charles E. Rossi, Assistant Director Division of PWR Licensing - A

SUBJECT:

CORRECTION OF STATEMENTS IN BVPS 2 SER PEGARDING TECHNICAL SPECIFICATIONS (TAC NO. 6?94?) ,

In response to your note nn the same subject, the Plant Systems Branch has reviewed SER Sections 6.4, 9.2.1.2, 9.5.4.2, 10.2. and 10.4.9 to assess the .

acceptability of plant-specific technical specifications for RVPS-7, which are different requirements than those prescribed for BVPS-1. Our assessment is enclosed. ,

n I \ No changes should be made to SRP Sections 6.4, 9.2.1.2, 9.5.4.? and 10.2.

D. Based on additional information provided by Amendment 12, the BVPS-2 TS for 10.4.9 can be modified to be consistent with BVPS-1.

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W har es E. Rossi, Assistant Director i Division of PWR Licensing - A

Enclosure:

As stated cc: L. Rubenstein l J. Calvo L. Hulman i

Contact:

R. Goel, x27162 )

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ENCLOSURE 6.4 Control Room Pressurization The control room habitability pressurization testing requirement is based on complying with Regulatory Guide 1.95 and Regulatory Guide 1.78, as stated in NUREG-0737, Item III.D.3.4. BVPS-? in FSAR Section 6.4 connitted to a control room design that meets the criteria of Pegulatory Guide 1.95 and 1.78. We found the applicant's comnitment acceptable. Consistent with these Regulatory Guides and licensing policy, our SFR dated October 19R5 stated that control ,

room isolation valve response time and pressurization leakage flow rates are appropriately listed in the technical specifications. Therefore, the RVPS-2 SER and technical specification (TS) is correct as stated.

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Because BVPS 1 and ? share a common control room the applicant should propose a change to BVPS-1 TS to make it consistent with PVPS-?.

9.2.1.2 Standby Service Water System (SSWS)

The Beaver Valley Unit 2 SER (NUREG 1057, dated October,1985) states that the applicant proposed technical specifications for periodic SSWS testing and inspection, to prevent biofouling and degradation of the SSWS. The SER also discusses the proposed flow tests that would be performed to demonstrate SSWS operabili ty. The staff SER is based on the applicant's proposal by letter dated September 14, 1985.

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Because of recent degradation problems associated with safety related service water systems at several plants (see NUREG-0933 and Generic Issue 511 the staff considers standby service water system operability to be an important safety concern. It is the staff's position that the SSWS should be subject to the applicable provisions of Appendix B to 10 CFR Part 50. As stated in the SER, the applicant committed to include the periodic testing and inspection provisions in the technical specifications to prevent SSWS degradation.

Therefore, the surveillance tests included in the Reaver Valley Unit 2 Technica)

Specifications should be retained.

9.5.4.2 Emergency Diesel Fuel Oil Storace and Transfer System The Beaver Valley Unit 2 SER (NUREG 1057, dated October 1985) stated the following as a staff position, with regard to fuel oil quality and testing:

The fuel oil quality and tests will conform with RG 1.137, Positions C.2.a through C.2.f, and the requirements will be included in the plant Technical Specifications.

Degradation of diesel fuel oil due to aging and contaminates (water, sediment, sulfur, etc.) may cause unavailability of the diesel generator due to improper combustion, corrosion of engine parts, gum, varnish and carbon deposits on engine parts, and clogging of fuel oil filters, and iniectors. The high quality fuel oil is necessary for the proper operation and assurance or on demand availability of emergency diesel generators at nuclear plants.

Industry standards-ANSI-N195, ASTF DE70, ASTM 0975, and ASTM D2974-and Regulatory Guide 1.137 referenced in SRP 9.5.4 provide the minimum quality requirenents that a fuel oil must meet in order to be classified as a diesel fuel oil. These cuality requirements specify the amount of contaminates (water, sediment, ash content, corrosion capability, etc.) that are allowed in diesel-

. quality fuel oil . The standards also specify how the sample is to be procured, when and how it is to be tested.

As stated in a letter from Darrel G. Eisenhut, dated lanuary 7, 1980, to all power reactor licensees, the staff considers diesel fuel oil quality to be a -

safety related issue, and subject to the applicable provisions of Appendix R to 10 CFR Part 50. Because of this, diesel fuel oil surveillance has been included

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in all versions of the Standard Technical Specifications and plant-specific Technical Specifications since 1979. Therefore, the SER reouirement for fuel oil testing in the Beaver Valley Unit 2 Technical Specifications should remain as stated in the staff SER, 10.2 Turbine Generator The Beaver Valley Unit ? SER (NUREG 1057, dated October 1985) states the following with regard to the inservice inspection program for the turbine valves:

"In Amendment 8 of the FSAR, the applicant committed to conform to the inservice inspection requirements ... of SRP 10.7 and the Standard Technicial Specifi-cations for the turbine valves."

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_4 The applicant originally proposed, in the FSAR, a different set of criteria for the inservice inspection (ISI) of the turbine valves. The staff reouested the applicant to ,iustify deviations and propose technical specifications for the ISI progran. However, the applicant opted and committed, as stated in the SER, to conform to the Standard Technical Specifications (STS) for turbine valve testing, which the staff accepted. Therefore, turbine valve testing will be in accordance with the STS, and will be included in the Beaver Valley Unit 2 Technical Specifications. -

10.4.9 Auxiliary Feedwater Systems -

4 The Beaver Valley Unit ? SER states that a minimum dedicated volume of water in the primary plant demineralized water storage tank (PPDWST) of 140,000 gallons is reserved for the AFWS, which the Technical Specifications so state.

This volume would ensure reactor coolant system cooldown to the RHP system cut-in temperature of 350*F in 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> (3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> in hot standby and 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for cooldown), assuming no makeup to the PPDWST. Due to level instrumentation design limitations, a TS requirement of 140,000 gallons is not possible. In FSAR Amendment 12, the applicant revised the usable PPDWST volume to be approximately 127,500 gallons, and proposed a Technical Specification limit of 127,000 gallons. As a result, the ddsign basis for the PPDWST has been changed to be consistent with the PVPS-1 TS; i.e., the PPDWST volume will support 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> at hot standby (rat r than 3-hours in hot standby plus 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />sincooldown). The PPDWST has connections to the 600,000-gallon

demineralized water storage tank, a non-safety tank, which is used for nomal make-up. However, the service water system may serve as a safety-related, long-term, backup source of AFK' for the steam oenerators. Based on the above, g the staff considers the PPDWST inventory of 127,000 gallons to be acceptable.

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