ML25197A086
| ML25197A086 | |
| Person / Time | |
|---|---|
| Issue date: | 12/10/1975 |
| From: | Kerr W Advisory Committee on Reactor Safeguards |
| To: | Anders W NRC/Chairman |
| References | |
| Download: ML25197A086 (1) | |
Text
ADVISORY COMMITTEE ON REACTOR SAFEGUARDS NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20565 Honorable William A. Anders Chairman December 10, 1975
- o. s. Nuclear Regulatory Conmission washington, DC 20555
SUBJECT:
INTERIM REPORT Cl'I FimTING NOCLFAR PI.ANT I&lr Mr. Anders:
niring its 188th Meeting, December 4-6, 1975, the Advisory Conmittee on Reactor Safeguards completed a partial review of the application of Off-shore Power Systems for a license to manufacture eight standardized Float-ing Nuclear Plant units in a shipyard-like facility located on Blount Island in Jacksonville, Florida. '!he COnmittee had previously reported to the Conmission on its review of the concept of a Platform Mounted Nuclear R:>wer Plant in its report of November 15, 1972. In addition, the Comnittee has had discussions of the Floating Nuclear Plant (FNP) concept in connection with the Atlantic <?enerating Station site review on which the Conmittee reported on O::tober 19, 1973. '!he manufacturing facility site was visited on O::tober 29, 1975 and the project was considered at a SUbcarmittee Meeting on O::tober 29 and 30, 1975, in Jacksonville, Florida. '!he project was also considered during the 187th Meeting of the Conmittee in Washington,
- o. c., November 6-8, 1975. niring its review, the Conmittee had the benefit of discussions with the Nuclear Regulatory Conmission (NBC) Staff, the
- o. s. Coast Glard, and representatives and consultants of Offshore Power Systems. '!he Conmittee also had the benefit of the documents listed.
'!he FNP will make use of the Westinghouse RESAR-3 Consolidated version four-loop pressurized water nuclear reactor having a core power output of 3411 MW(t). 'Ibis reactor design is similar to that utilized at the catawba Nuclear Station Ulits 1 and 2, reported on by the Committee in its report of November 13, 1973. '!he scope of the FNP design includes the Nuclear Steam SUpply System (NSSS) and the Balance of Plant (BOP).
'!he complete system, which is to be mounted on a large floating platform, represents a standard unit which is being designed for use at sites wich fall within an envelope of parameters or specifications. '!he plant design includes specific requirements for major components, piping systems, and other information necessary to ensure that both the t-..<SSS and BOP are designed to protect the system from site-related hazards.
Application of the fl.1-P concept will require an evaluation of each site to confirm its acceptability within the given envelope.
569
Honorable William December 10, 1975 With respect to the site envelope, the Conmittee recarmends that further consideration be given to methods for the assessment of probabilities for given accident events, such as those involving ships. Rather than treat each potential accident situation as a separate class of event, it may be mre appropriate in some cases to evaluate the significance of a given class of event on the basis of the total probability of all events within that class.
'Ihe NRC Staff has identified several issues which remain to be resolved.
Qle pertains to the acceptability of criteria for containment shell buckling, including the behavior of the shell during construction. To be included in the assessment of this issue are the effects of deforma-tion of the containment foundation. Another issue concerns the effects and consequences on the FNP of the explosion nearby of a petroleum tanker.
'Ihese matters should be resolved in a manner satisfacto1y to the NRC Staff.
'Ihe Conmittee wishes to be kept informed.
Evaluation of the F.mergency Core Cooling System (ECCS) design in accor-dance with Appendix K of 10 CFR Part 50 is also an outstanding issue which has been identified by the NRC Staff. In this regard, the Conmittee has special interests relating to detailed assessments of the upper head injection system, the resolution of potential problems with the ice condenser pressure suppression system, and the margins available in the ECCS.
'Ihe Corrmittee wishes to review the design and analysis of both of these systems prior to the NRC issuance of a license to manufacture the FNP units.
In the course of its review, the Cormnittee noted other areas wherein it wishes to be kept informed. 'Ihese include any problems associated with turbine-generator alignment; hull-coupled vibrations (particularly as these relate to the potential of turbine failure and the generation of missiles); analysis of stresses on key components associated with platform towing operations; and the location and range of instruments for determining the nature and course of any accidents.
Since the FNP is a novel design requiring unusual structural reliability there is a need to develop plans for verification of structural design and to define the requirements for strain and deformation measurements, visual inspection during operational testing, and nondestructive inspec-tion of critical FNP structures subsequent to operational loading. 'Ihe Conmittee wishes to be kept informed.
570
Honorable William December 10, 1975 Consideration should be given in design to the possible provisions for redundant mooring systems.
'lhe Coomittee recanmends that the NRC Staff and the Applicant review further the design features that are intended to prevent the occurrence of fires and to minimize the consequences to safety-related equipnent should a fire occur. '!his evaluation should include a* review of systems for detecting and protecting against fires, both within and outside the plant. '!his matter should be resolved to the satisfaction of the NRC Staff. 'lhe Committee wishes to be kept informed.
Also to be evaluated are the consequences of, and any safeguards necessary to cope with, a major accident which could lead to the dispersal of a significant quantity of radioactive materials into the water surrounding the FNP. 'lhe Committee mderstands that this item is being evaluated by the NRC Staff and the Applicant. '!he Commi.ttee will reserve judgment on this item, which is both site and plant related, mtil it has had an opportmity to review and evaluate the relevant information.
'lhe Committee suggests that analyses be made of any possible increases in the protection of public health and safety which may be obtained by an increase in containment design pressure.
'!he Applicant has suggested the use of a coating and a cathodic system to protect the platform against corrosion. '!he proposed cathodic system appears to be suitable for the mderwater portion of the platform; however, additional attention should be given to means for protecting the critical wave and splash mne areas where repair or renewal may not be practical Wlder the anticipated operating conditions of the FNP.
Because operating and maintenance personnel may be on board the floating platform for extended periods of time, and because shielding may be limited due to weight restrictions and limitations on available space, it is possi-ble that doses and dose rates to personnel on the FNP may be greater than for land-based units. As a result, the Committee believes that special consideration should be given to conformance with the "as low as reasonably achievable" criterion.
'!he Committee believes that the Applicant and the NRC Staff should continue to review the FNP design for features that could reduce the possibility and consequences of sabotag.
571
lk>norable William December 10, 1975
'!he Conmittee recorrmends that further attention be given to the possi-bility of extended loss of off-site power due to natural events or other causes, and the potential impact of this possibility on the requirements for emergency AC power.
Generic problems relating to large water reactors are discussed in the Conmittee's report dated March 12, 1975. '!he Conmittee believes that procedures should be developed to incorporate approved resolution of these items into the FNP.
'!he Advisory Conmittee on Reactor safeguards believes, that subject to the foregoing and to other applicable matters discussed in its reports of November 15, 1972 and <xtober 18, 1973, the Floating Nuclear Plant units can be constructed with reasonable assurance that they can be operated without undue risk to the health and safety of the public.
'!he Conmittee will cooplete its review of this application when the necessary additional information has been developed.
Sincerely yours,
~
572
- w. Kerr Oiairman
Honorable William A. Anders
-s-December 10, 1975 References
- 1.
Floating Nuclear Plant (FNP) Plant ~sign ReIX)rt (PDR) Volumes 1-8
- 2.
Amendments 1 through 17 to the PDR
- 3.
safety Evaluation ReIX)rt by the Division of Reactor Licensing (DRL),
dated September 30, 1975
- 4.
Memorandum of tbderstanding J?etween the u. S. Coast Guard {USCG) and the u. s. Atomic Energy Conmission for Regulation of Floating Nuclear R>wer Plants, dated January 4, 1974 S.
Ietter, dated September 5, 1975, Offshore R>wer Systems (OPS) to DRL, transmitting Westinghouse ReIX)rt entitled *valve Reliability, TUrbine Inlet Valves," dated August 1975
- 6.
Ietter, dated September 2, 1975, USCG to DRL, providing comments on Offshore R>wer Systems ReSIX)nse to Staff R>sition Concerning Olarpy V-Notch Testing of Weldments
- 7.
Ietter, dated August 25, 1975, OPS to DRL, providing additional turbine missile infoanation
- 8.
Ietter, dated August 11, 1975, providing information on Emergency Core Cooling System Perfoanance
- 9.
Ietter, dated August 8, 1975, OPS to DRL, transmitting Revision 1 to the Platform Hull Drydocking Fquivalency document
- 10. Ietter, dated June 3, 1975, OPS to DRL, providing information on turbine missile penetration of steel barriers
- 11. Ietter, dated May 21, 1975, OPS to DRL, regarding external fire protection system
- 12. Ietter, dated April 3, 1975, USCG to DRL, providing plan regarding details of exterior fire protection
- 13. Ietter, dated March 10, 1975, USCG to DRL, providing comments on Platform Hull Corrosion Control Plan
- 14. Ietter, dated January 30, 1975, OPS to DRL, regarding Damaged Platform Stability 573
Honorable William December 10, 1975 References - Continued
- 15. Ietter, dated January 23, 1975, OPS to DRL, transmitting report on Control R:>d Drive Mechanism Analysis performed by 'Westinghouse
- 17. Ietter, dated January 3, 1975, USCG to DRL, providing C<X'IIEnts on fracture toughness testing of hull steel for floating nuclear plants
- 18. Ietter, dated December 17, 1974, OPS to DRL, transmitting errata sheet for report on external fire protection
- 19. Ietter, dated December 5, 1974, OPS to DRL, regarding procedures for structural plans
- 20. Ietter, dated November 22, 1974, OPS to DRL, transmitting revision to EkilJivalency Demonstration document
- 22. Ietter, dated November 13, 1974, OPS to DRL, transmitting nonproprietary report on Emergency Trip Systems and m.trasonic Inspection
- 23. Ietter, dated November 12, 1974, OPS to DRL, transmitting document entitled *Floating Nuclear Plant Platform Hull Corrosion Control Plan
- 24. Ietter, dated November 12, 1974, OPS to DRL, transmitting 'Westinghouse Electric Corporation reports
- 25. Ietter, dated October 16, 1974, USCG to DRL, enclosing August 29, 1974 letter fran OPS and USCG's October 11, 1974 letter to OPS
- 26. Ietter, dated October 8, 1974, OPS to DRL, transmitting report entitled
- wind and Wave Persistence and Forecast Iead Times for Four Offshore locations" 574
li>norable William December 10, 1975
- 27. letter, dated September 26, 1974, OPS to DRL, transmitting position on Anticipated Transients Without Scram
- 28. letter, dated September 6, 1974, OPS to DRL, transnitting Westinghouse report entitled *A Conparison of l'estinghouse Overspeed Protection to the Requirements of IEEE 279"
- 29. letter, dated August 29, 1974, OPS to DRL, transnitting three westing-house reports
- 30. letter, dated August 12, 1974, OPS to DRL, providing clarifying information regarding the calculation of transmission line reliability
- 31. letter, dated August 8, 1974, OPS to DRL, transmitting MIDAS code report
- 32. letter, dated August 7, 1974, OPS to DRL, transmitting revision to
&nergency R>wer F.quivalency document
- 33. letter, dated August 2, 1974, OPS to DRL, transmitting westinghouse Electric Corporation report on Analysis of the Probability of the Generation and Strike of Missiles From A Nuclear 'I\u:bine
- 34. letter, dated July 2, 1974, OPS to DRL, transmitting doctnnent entitled *Platform Inclinations n.te to Damage to Any Cne Side"
- 35. letter, dated July 2, 1974, OPS to DRL, transmitting revision to
&nergency J?Ower F.quivalency doctnnent
- 36. letters, dated March 29 and February 25, 1974, USCG to DRL, regarding selection of hull material for Floating Nuclear Plants
- 37. letter, dated January 7, 1974, OPS to DRL, transmitting information on Anticipated Transients Without Scram
- 38. letter, dated Q::tober 26, 1973, OPS to DRL, providing interim informa-tion regarding Nuclear Plant Arrangement and Ice Condenser ~sign 575