ML20235F380
| ML20235F380 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Zimmer |
| Issue date: | 09/17/1971 |
| From: | Bush S Advisory Committee on Reactor Safeguards |
| To: | Schlesinger J NRC COMMISSION (OCM) |
| Shared Package | |
| ML20234A777 | List:
|
| References | |
| FOIA-87-40 NUDOCS 8707130357 | |
| Download: ML20235F380 (13) | |
Text
{{#Wiki_filter:_ _- __ I = g ADVISORY COMMITTEE ON REACTOR SAIEGUARDS . UNITED STATEF ATOMIC ENERGY COMMISSION WASHINGTON D.C. 20545 ' September 17, 1971 Honorable James R. Schlesinger Chairman U. S. Atomic Energy Commission Washington, D. C. 20545.
Subject:
REPORT ON WILLIAM H. ZIMMER NUCLEAR POWER STATION, UNIT 1
Dear Dr. Schlesinger:
At its 137th meeting, September 9-11, 1971, the Advisory Coarnittee on Reactor Safeguards completed its review of the application from the Cincinnati Gas and Electric Company, the Columbus and Southern Ohio Electric Company, and the Dayton Power and Light Cumpany for a permit to construct the William H. Zimmer Nuclear Power Station,. Unit 1. The Cincinnati Cas and Electric Company is responsible for the. design, construction, and operation of the plant and is author-ized to act as sole agent during construction and for licensing nego-tiations. The project was considered at Subcommittee meetings -on August 27, 1971, at the plant site, and on September 1 and September 8, 1971, in Washington, D. C. During its review the Committee had the benefit of discussions with representatives and consultants of the applicante, Sargent and Lundy, the General Electric Company,' and the AEC Regulatory Staff. The Committee also had the benefit of the documents listed below. The Zimmer Station will be located in Ohio on a 635-acre site on the Ohio River approximately 24 miles southeast of Cincinnati and one-half mile north of Moscow, Ohio. The population of Moscow is estimated by the applicants to be 348. The nearest population center is Covington, Kentucky which is located 20 miles northwest of the site and has a population of 60,000. The low population zone radius is 3.0 miles within which the 1960 population was less than 1,900 and the projected 1985 population less than 2,800. The projected 1985 population within 10 miles of the site is 30,100. The exclusion zone has a minimum radius of 1,250 feet, is bounded on the north by U. S. Route 52, and includes a small manufacturing plant 1ocated on the periphery. Provi-sions have been made to evacuate the employees of this plant in the unlikely event of an accident. 'I 8707130357 870610 PDR FOIA THOMASB7-40 PDR I
.t I ( Honorable sames R. Schlesinger September 17, 1971 The applicants h,ve studied design features to mnke tolerable the consequences of failure to scram during anticipated transients, and have concluded that automatic tripping of the recirculation pumps and injection of baron could provide a suitable backup to the control rod system for this type of event. The Committee believes that this retirculntion pump trip represents a substantial improvement and should be provided for the Zimmer reactor. However, further evalua-tion of the sufficiency of this approach and the specific means of implementing the proposed pump trip should be made. This matter should be resolved in a manner satisfactory to the Regulatory Staff and the ACRS during construction of the reactor. The radioactive waste disposal systems process high and low conduc-tivity liquid wastes by demi'eralizers or evaporators and the n decontaminated effluent is recycled to the condensate storage tank for reuse. Chemical and detergent wastes normally are to be processed through evaporators and, if necessary, further processed by demineralizers before discharge. The gaseous waste treatment system includes a high temperature catalytic recombiner followed by a 30-minute holdup system. The applicants will provide an additional holdup system which results in the substantial reduction + of all isotopes except long-lived krypton. The applicants have i stated that both 'the liquid and gaseous waste handling systems kill be used to the fullest extent and 'will limit releases of radioactiv-j ity or exposures to man to values,less than 'those'specified in the ~ proposed 10 CFR 50, Appendix I. An envir'onmental monitoring program has been established, and the applicants have stated that it will permit the calculation of radiation exposures to man from records of radioactivity released from the pla,nt. The applicants have stated a system will be provided to control the concentration of hydrogen in the primary containment that might follow in the unlikely event of a loss-of-coolant accident. The Committee believes that the containment should be inerted and that the hydrogen control system should be designed to maintain the hydrogen concentration within accertable limits using the assump-l tions listed in the AEC Safety Gt.ide 7, Control of Combustible Gas Concentrations in Containment Following a Loss of Coolant Accident. The applicants' pipe whip criteria consider both longitudinal and circumferential pipe breaks and provide for the installation of piping restraints as required to prevent damage to ersential reactor coolant systems and equipment or to the containment. 1
) 0 4 f UNITED STATES D ATOMIC ENERGY COMMISSION WASHINGTON, D.C. ~20545 No. P-382 FOR I ANEDI ATE RELEASE
Contact:
Michael L. Butler (Thursday, November 16, 1972) Tel. 973-7771 ADDITIONAL HEARING SESSION SCHEDULED FOR OHIO NUCLEAR PLANT ON NOVEMBER 21 An additional evidentiary session in the proceeding which considered Cincinnati Gas 6 Electric Company's application for a cons t ruct ion permit to build the William H-. 2irner nuclear station will be held on November 21 in Washington, D. C. The session will begin at 10 a.m. on Tuesday, Novenber 21, 1972, in Suite 720, Vanguard Building, 1111 Twentieth Street, N. W., Washington, D. C. A const ruction permit authorizing the company to build the Zimmer facility was issued on October 27, 1972.
- However, the Atomic Safety and Licensing Appeal Board, in reviewing the initial decision rendered in the proceeding, directed that the record be further developed to include consideration of a dry cooling tower as an alternative cooling method.
As proposed, the facility will use a natural draft cooling tower. The Appeal Board's order does not affect activities authorized unde r the const ruction permit. mems y w.:*Y s~ g/p.. p r.. g-g
02 V t UNITEp ST ATES ~ Q aioMiC ENERGY COMMISSION WASHINGTON, D.C-20545 No. P-357 FOR ISBIEDIATE RELEASE Contact Clare 31iles (>!on d ay, October 30, 1972) Tel. 973-7771 AEC ISSUES CONSTRUCTION PERb!IT FOR NUCLEAR POWER PLANT IN OHIO l 'I h e Atomic Energy Commission has issued a permit to Cincinnati Gas and Elect ric Company and two othe r Ohio utili-ties for const ruction of the Km. H. Zimmer Nuclear Power Station to be located near 31oscow, uhjo. The other utilities are Columbus 5 Southe rn Ohio Elect ric Company and the Dayton Power S Light Company. l 1 The facility will use a boiling water reactor and will have a net e lect ri cal capacit y of about 807,000 kilowatts. The site for t he s t at ion is on the east bank of the Ohio Rive r in Washington Tovnship, Clermont County, 24 miles southeast of downtown Cincinnati. Issuance of the permit follows completion of reviews by the AEC Regulat ory st af f and the independent Advisory Committee on React or Safeguards and a public hearing on radiological and environmental mat t e rs conducted by an Atomic Safety and Licensing Board. The Licensing Board held sessions of the hearing in Cincinnati on June 1 and 2 and September 20, 1972, and issued a decision on October 19 authorizing issuance of the pe rmit. 4 7 -- ~. *~.=W==- L:. T. [f e.. ?;;{- l,l C m DZ L n = n n.; "S 5'- G4 y x - - - - - -
UFHCHAL USE ONLY EXCERPT FROM
SUMMARY
OF 137TH ACRS MEETING
SUMMARY
- SPECIAL PROJECTS 137th Meeting Summary Meeting Date:
September 9-11, 1971 3.4 William H. Zimmer Nuclear Power Plant Unit 1 3.4.1 Executive Session Dr. Kaufman described the features of the proposed plant and reviewed the current status of the Subcommittee and Regulatory Staff evaluations of Zimmer. Only matters relating to H2 e ntrol, containment inerting, and design standards for the main steam line remain to be resolved. In discussion,it was brought out that: (a) The GE 1969 product line will be introduced in Zimmer, and it embodies a number of improvements over the 1967 line; (b) Meteorological data being obtained by the applicant at the site is expected to show that the PSAR assumptions were too conservative. (c) The implied use of check valves as an alternate to constraints for avoiding pipe whip problems should be explored further and with regard to the number of additional valves that might be required. (d) Problems and disagreements related to Class I seismic design of the main steam line should be clarified. 3.4.2 Meeting with the Regulatorv Staff Discussion with the Staff, primarily Messrs. Case and Stello, touched on the following subject areas and provided information as noted. (a) The absence of agreed-upon standard criteria and requirements for seismic design of critical piping is having an increasing impact on the ef ficiency if not the effectiveness of adminis-l tration of the regulatory process. l (b) The Staff position with respect to seismic design of the main steam line is based upon considerations of earthquake prob-ability, unpredictable ef fect of a DBE on the line, and the doses resulting from steam line failure with LOCA. A con-sistent position with respect to minimum line size (2-1/2 inch) to be included is also an objective. A Safety Guide might be used to obtain compliance. (c) As a minimum, the applicant must perform a seismic Class I analysis of the piping and supports at all interfaces with ) Class I structures. (d) The check valves mentioned in connection with pipe whip are l not extras. Piping breaks on the unpressurized side of the l check valves would not cause pipe whip. It was noted that Date Issued: September 21, 1971 OFFHCHAL USE ONLY 1 D
LIFHCHAL USE ONLY 137th. Meeting Summary Meeting Date: September 9-11, 1971 this is the first applicant to agree to such extensive pipe whip protection. Where installed check valves will not preclude pipe whip, other devices will be provided for this protection. (e) It is difficult to make generalized comparisons of the relative adequacy of the ECCS systems at Newbold and Zimmer. For some types of breaks, one may be better than the other. 3.4.3 Meeting with Cincinnati Gas and Electric Company Mr. Dickhoner and other members of the applicant's staff reviewed the Zimmer project activities to date and described, with the aid of illus-trationa, the site and the proposed methods for taking care of particular safeguards problems related to floods, earthquakes and meteorological conditions. Design features of the plant and its systems and components were also presented in response to expressions of Committee interest in specifle items. The following information was developed in discussions involving the applicant, principal contractors and members of the Committee. (a) Surface soils with unsatisfactory liquefaction characteristics are being removed and replaced,with compaction,to provide ade-quate support for the foundations of critical buildings. (b) Steam piping (2-1/2-inch diameter and larger) from the reactor vessel through the isolation valves will be analyzed to Class I seismic criteria. + (c) Main steam line piping, eight inches and above, between the outermost isolation valve and the steam tunnel bulkhead,will be analyzed in accordance with Class II requirements, except that at interfaces a simplified Class I analysis will be used. (d) Main steam line piping between the tunnel seal wall and through the turbine stop valve is not proposed to be designed to Class I seismic standards,primarily because of difficulties associated with the turbine stop valve which is a control valve and an integral part of the turbine steam chest. (e) The main steam line isolation valve seal system has not been selected yet, but it will be designed as an engineered safety feature. (f) The reliability of the 1969 product line HPCS with diesel electric drive is expected to be 0.98 as compared with 0.92 for the 1967 HPCI. Date Issued: September 21, 1971 OFFECHAL USE ONLY
l OL IHCHAL USE ONLY ' b ( 137th Meeting Summary Meeting Date: September 9-11, 1971 I (g) The applicant proposes to make provisions for installing inert-ing equipment, but would review the need for this in the light of metal / water reaction data and other design information prior to the 0.L. stage and would install inerting equipment if rwquired. (h) The applicant has used a 2*/. metal / vater reaction basis for post-LOCA analyses rather than the 5% basis of the AEC. t (i) The applicant proposes an H2 purge system utilizing two deep-bed charcoal filters, but will continue to investigate H2 recombiners. (j) Flood protection of the reactor building will be provided to an elevation of +546 feet MSL (about 26 feet above grade) with wave protection to +550 feet. (k) Zimmer core-spray nozzles introduce a new design concept for improved inspectability. 3.4.4 Caucus The Committee recognized the points of current disagreement between the Staf f and applicant, but the consensus of the members was that these matters and the state of incomplete definition of other systems and components for Zimmer were not unusual in comparison with other plants at this stage of the licensing process. It also appeared to the Committee that avenues for solution of these matters were known and that it was unlikely that any would fail to be resolved within a reasonable I period of time. On the basis of these considerations the Committee determined that a letter could be written, but that the letter should: j 1 recognize the GE 1969 product line modifications e indicate the importance the Committee assigns to the e integrity of the main steam line. (The Committee agreed that it is not appropriate to require Seismic ) Class I design of the turbine stop valve,although its integrity should be assured. Detailed resolution l would be lef t to the Staf f.) l require that the isolation valve seal system be classed e as an engineered safety feature. Date Issued: September 21, 1971 OFFECHAL USE ONLY ____-_..______.___________]
PFFHCHAL USE ONL1 137th Meeting Summary Meeting Date: September 9-11, 1971 3.4.5 _ Conclusion Dr. Bush addressed Mr. Dickhoner and stated that the Committee beli it can write a letter favorable to the construction of the Zimmer plant. For purposes of clarification of the Committee's position regarding the seal system, there appears to be some discrepancy between what was said and what was read. The Committee will look at the amendment. If it does not convey the same meaning as your verbal agreement, the Committee will assume that the verbal expression of intent applies. i 6 t Date Issued: September 21, 1971 1 i I OFFHCHAL USE ONLY
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