ML20076C818

Forwards marked-up Revised Response to Question 460.09 of NRC 820825 Request Re GESSAR-II Std SAR

ML20076C818
Person / Time
Site:	05000447
Issue date:	05/18/1983
From:	Sherwood G GENERAL ELECTRIC CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
JNF-033-83, JNF-33-83, MFN-087-83, MFN-87-83, NUDOCS 8305200157
Download: ML20076C818 (6)

Text

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GENER AL h ELECTRIC NUCLEAR POWER SYSTEMS DIVISION GENERAL ELECTRIC COMPANY,175 CURTNER AVE., SAN JOSE. CALIFORNIA 95125 MFN 087-83 (408) 925-5722 M/C 682 JNF 033-83 May 18, 1983 U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, DC 20555 Attention- Mr. D.G. Eisenhut Division of Licensing Gentlemen:

SUBJECT:

IN THE MATTER OF 238 NUCLEAR ISLAND GENERAL ELECTRIC STANDARD SAFETY ANALYSIS REPORT (GESSAR II) DOCKET NO. STN 50-447 REVISED RESPONSE TO QUESTION 460.09 Attached please find a revision to Question 460.09 of the Commission's August 25, 1982 information request.

Sincerely, Glenn G. Sherwood, Manager Nuclear Safety & Licensing Operation Attachment

cc

F.J. Miraglia (w/o attachment) C.0. Thomas (w/o attachment)

D.C. Scaletti L.S. Gifford (w/o attachment) 8305200157 830518 PDR ADOCK 05000447 A PDR 6

. = . . - ____

238 NUCLEAR ISLAND Rsv. 14 19.3.1.6 QUESTION / RESPONSE 1.6 (460.09)

QUESTION 1.6 ( RbYk bbh]

i l ' Provide a table in Section 1.8 of your FSAR comparing the design features of the liquid, gaseous and solid radwaste systems with each position of Regulatory Guide 1.43, Revision 1 (October 1979). Justify each position for which an exception is taken. If information is provided in other sections of i

the FSAR for the individual items, cross-references to these

, sections are acceptable. We consider compliance with Section C.5 I

of Regulatory Guide 1.143 to be essential. Verify whether

! you satisfy our acceptance criteria for concentrations of radioactive constituents in accordance with Item II of l .Section 15.7.3 of the Standard Review Plan (SRP). Our position is that limiting doses to 0.5 rems, as stated in Section 11.3.2.20 of your FSAR, is not an acceptable alterna-tive. (1.8, 11.2, 11.3 and 11.4)

RESPOUSE 1.6 l

l The offgas system meets the requirements of Position C.2.1.3

! of Regulatory Guide 1.143 by the following:

(1) The offgas delay tanks have no natural frequencies between 2 and 35 Hz.

l l (2) The stress in the supports, based on a horizontal static equivalent force of 0.15g is less than 1.33 times the allowable stress level of AISC Manual of Steel Construction 7th Edition, 1970.

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1 238 NUCLEAR ISLAND Rev. 14 19.3.1.6 QUESTION / RESPONSE 1.6 (460.09) (Continued)

(3) The tanks are located on the base mat of the buildiet erntaining th-- Lv-b w4.

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his method of compliance has been accepted by the NRC in 9 G-0174. k In addition, the entire Offgas System meets the following requirements:

i (1) The system design pressure is at a minimum 350 psi and in part is as high as 1000 psi while the system operating pressure is 6.7 psig.

(2) The material of construction is required to demonstrate high notched stress ductility.

(3) All pressure retaining butt welds are 100% radiographed.

(4) The system must pass a 10 s atm cc/sec helium leak test.

(5) The buildings housing the Gaseous Radioactive Waste Processing System will be designed in accordance with the Uniform Building Code.

A conservative analysis of the dose consequences of failure of this system has been provided in topical reports NEDE-21056-P and NEDE-21056-1P.

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mJt-natcesr1caoss re. sa 19.3.1.6 QUESTION / RESPONSE 1.6 (460.09) (Continutd)

The above not withstanding, the last paragraph of Section A of BTP ETSB 11-5 calls for the analysis of a single failure of an active component in the waste gas system as providing

" adequate and acceptable design solutions..."

As a part of the design of the GESSAR II Offgas System, the system does not release any activity untreated through a single active component failure. An operational error could bypass the main charcoal delay tanks; however, the post-treatment monitor would cause closure of the redundant bypass valves. The post-treatment monitor is single.-failure resistant.

In the event the preset Hi-Hi-Hi value of the post-treatment monitor is exceeded, a valve downstream of the monitor auto-matically closes and causes the closure of the normal system drains to further present inadvertent bypass.

Finally, ap' plication of the BTP ETSB 11-5 100 pCi/sec/MWt (after 30 min decay) source term to the standard site yields a site boundary dose less than 400 mrem.

Description of compliance with the geology and hydrology considerations of NUREG-0800 Subsection 15.7.3 is the responsi-bility of the Applicant.

I i

19.3.1.6-3/19.3.1.6-4

@%%I MM 22A7007 238 NUCLEAR ISLAND Rev. 0 11.3.2.20 Seismic Design Equipment and components used to collect, process, or store gaseous radioactive waste are classified as non-Seismic Category I.

Conservative analyses presented in Section 15.7 demonstrate that equipment failure will not result in doses exceeding the 0.5-Rem 4

guidelines of Regulatory Guide 1.29.

The support elements, including the skirts, legs and anchor bolt-ing, for the charcoal adsorbr r tanks' of the offgas system are o

designed as follows:

(1) the fundamental frequency of the charcoal adsorber tanks including the support elements is greater than 33 Hertz; (2) the charcoal adsorber tanks are mounted on the base mat of the building housing the tanks;

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(3) the charcoal adsorber tanks including the support ele-ments are designed with a horizontal static coefficient of 0.15 g; and (4) the stress levels in.the support elements of the charcoal adsorber tanks shall not exceed 1.33 times the allowable stress levels permitted by the AISC Manual of Steel Construction, Seventh Edition, 1970.

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requirements of Regulatory. Guide 1.143 4fe rarly Branch Technic s Pcsitivu CTC2 "c. 11 l' 'Rcfcr;ne" 0 1 f

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,wg p, A program will be establislied that is sufficient to assure that the design, construction, and testing requirements are met. The follow-ing areas will be included in the program: ,

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unsona At eensuur 238 NUCLEAR ISLAND Rav. 4 11.3.5 References (Continued)

3. Siegwarth, D. P., Measurement of Cynamic Adsorption Coefficients for Noble Gases on Activated Carbon, 12th AEC Air Cleaning Conference.

4. Standards for Steam Surface Condensers, Sixth Edition, Heat Exchange Institute, New York, NY (1970).

5. Underhill, Dwight, et al., Design of Fission Gas Holdup Systems, Proceedings of the Eleventh AEC Air Cleaning Conference, 1970, p. 217.

6. Nesbitt,-L. B., Design Basis for New Gas Systems, July 1971, NEDE-lll46 (General Electric Company Proprietary).

7. N66 SJAE Offgas Treatment System - Amendment 1 (supple-ments Licensing Topical Report, August 1978 (NEDE-21056-3-P) (Proprietary).

8. NUREG-0124 (Supplement 1 to NUREG-75/110) Safety Evalua s tion Report. Related to the Preliminary Design of the GESSAR-238 Nuclear Island Standard Design, US Nuclear Regulatory Commission, September 1976, pages 3-l and 3-2.

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