ML19221A597

TMI Miscellaneous Notes & Charts Including Info Re long-term Containment Configuration,History of Core Damage,Assessment of Core Integrity & Operation Modes During long-term Cooling

ML19221A597
Person / Time
Site:	Crane
Issue date:	05/18/1979
From:	INDUSTRY ADVISORY GROUP
To:
References
OLP-790518, NUDOCS 7905230285
Download: ML19221A597 (15)

Text

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INDUSTRY ADVISORY GROUP DOCUMENT CONTROL Submitted Task Memo Report Title By Da te No. No. ~ , Bebiv' c sf RCS with Steam Generators in C. Solbrig 4/10/7C 4 I A-4 -l

• R. Muench C3 ting Mode

'J. Thiesingl H. Lawroski J. Palladinc I B. Campbell 1 }RCSBehavior J. Thiesing 4/9/79 4 IA-4-2* 4 IA-4b Use of CFT's to Aid Reflux Boiler Cooling R. Muench 4/12/75 Techniques Desired Long Term Containment Configuration C. Solbrig 4 /1 1/ 75 Sa&b IA-Saab Fuel Temperature Thermocouple Readings During Campbell & 4/1 2/75'10b IA-10b* Pressure Transients From 4/9/79-4/12/79 Kolar Coments on History of Core Damage J. Dietrich 4/13/75' 6b IA-6b* Simulation of a Fire in Containment-System J. Thiesing 4/1 3/75 3 IA-3* Capabilities-Containment Response Assessment of Core Integrity C. Solbrig Sfl3/751 6a IA-6a* Evaluation of pros arJ cons of alternate RHR H. Lichten-4/15/75'15 I A-l'5* system and make recomendations berger h Addendum to IAG Report on Task 15 H. Lichten-4/17/79 15-IA-15* berger Addenda: Order of installation on recorders G. Zigler 4 /1 8/75 1 16a I A-10a* Evaluate the Effect of Non-Condensables In the D. Ditmore 4/17/79 10c I A-10c

• Reflux Bo ling Mode i

Modes of Operation During Long-Term Cooling C. Solbrig 4/18/7 ) 10a I A-10a

• Examine the High Counting Rate of BF Neutron M. Shulcz 4/20/7 3 23 IA-23*

3 Detector Detemine Likely Source of Gaseous Activity in W. Stroupe 4/20/7 9 24 IA-24* Auxiliary Building TC's to be Used for N.C. criteria W. Stroupe 4/20/79 25c IA-2Sc* Criteria for Aborting Attempt to Establish M. J. Kolar 4/19/70 21 1A-21* Natural Circulation Detemine Containment Response to Loss of all J. W. Thiesing Containment and all Decay Heat Rejected to ~4/21/79 ' 27 IA-27* the Containment 165 25 2

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~ INTRODUCTION (n Problem Statement - Evaluate the pros and ccns of the alternate RHR system and provide recommendations. / Sumary of Action - The above problem was presented

• .o the Industry Advisory Group which has made a brief inv.stigation, sumarized the perceived risks and advantages in regard to the various p

alternates and developed a set of recomendations. +-. RECOMMENDATIONS V The recomendations of the group are as follows: p 1. Upgrade the present RHR systems to improve their reliability for long term h operation uno'er high radiation and minimum maintenance conditions. Make j i only those changes which are considered to-be absolutely necessary. Some'f7 suggested areas are: - revise the pump motor lubricating system to function with the expected radiation exposure; p - remove the strainers fran the pump suction pipes if this has not already g,, been done; - add remote instrumentation where such will be helpful in understanding system conditions (also consider relocating gresent instrtsnentation to minimize personnel exposures); - add drip catchers, dikes, or other means to minimize problems due to leaks; - add shielding in strategic locations to permit access with tolerable personnel exposures. 2. Arrange to have B&W engineers participate in the improvement program for the present RHR systems and the design of the new skid mounted RHR system. S Gk 3. Review all available data on operation of other RHR systems of the same design to identify problems and corrective actions taken. 4. Continue the design and construction of the skid mounted system including the excavation and other site work necessary i.o allow penetration of the auxiliary building wall. 5. We favor the addition of the new pipe connections to the existing RHR from 1 the inside of the auxiliary building without breaching the wall if practical. Thus, providing that levels of exposure allow, we recomend installation of the ties and valves in the three RHR lines and stub off inside the building wall in such a location as to allow connection at a later date when the building wall would be penetrated from the outside. p a.A D L P~6 6 0^ ,,fluk. dei W y b d /"~M " M cs vD A'##. 165 253

~ RECOMMENDATIONS (CONT.) Page 2 6. If this is not practical, then build a valve pit outside of and against the auxiliary building of sufficient size to allow working space for cutting through the building wall and making up the piping. The valve pit should be essentially an extension of the auxilicry building and should meet all the design requirenents of that building for handling and containing radioactive materials and for protection against external loadings; e.g., seismic, plane crash, etc. Once this valve pit is completed and sealed off, cut through the auxiliary building wall and install the pipe connections and valves. 7. Start now on a permanent building including planning for clean-up of the water systems and decontamination of the buildings. This building should have all the features necessary to the operation of radioactive material handling systems. The location selected for the skid mounted RHR system appears to be the best site for this permanent building. There should be' no temporary building as currently planned. It's design should be revised to be permanent as described here. 8. Notwithstanding any of the above, the existing RHR systems availability should be maintained and, should the necessity arise, use the present systems. Once the new RHR system is installed in a structure equivalent to the present auxiliary building, use this new system in preference to the present systems. We strongly recommend against hooking up and operating the alternate RHR system without these provisions, unless it is deemed as absolutely necessary. ALTERNATE RHR RISKS AND ADVANTAGES 1 The proposed alternate RHR (Reactor Heat Removal) system design was reviewed i to identify potential risks and advantages which should be considered prio" to breaching the reactor auxiliary building wall to make the final hook-up. The primary risks identified in order of decreasing importance are as follows: 1. The new system, as currently planned, will bring primary coolant outside the primary containment and auxiliary building and into a temporary housing of questionable integrity. 2. There is a high potential for impact on the on-going recovery program en the island due to radiation leakage to the local surroundings unless the temporary RHR building can be well-shielded and have provision for tight leakage control. 3. Cutting into and opening the auxiliary building, as currently planned, basically involves penetration of an important boundary to radiation release for the duration of the cut and repair, unless a permanent concreta structure with leak tightness, equal structural integrity to the auxiliar, building and external access provision is first constructed around the intended location for the cut. 165 254

W ALTER 4 ATE RHR RISKS AND ADVANTAGES (CONT.) Page 3 The secondary risks identified in order of decreasing importance are as follows: 4. Cutting into the existing RHR system suction pipe will remove both the existing RHR systems from service for the duration of the cut and closure, ar~' will also run the risk of high dose due to possible suction line isolation valve leakage. The dosage risk also exists as each discharge line is cut into. However, since these cuts and closures smuld be made one line at a time there would always be at least one RHR systen available for service if needed. 5. There would be a high risk of increased contamination of portions of the existing RHR system, i.e. discharge piping downstream of the RHR heat exchangers, and suction piping upstream of the RHR pumps, if the new alternate RHR system were used first, instead of using the existing RHR. 6. There is some risk thet the very accelerated schedule for completing the design, fabrication and testing of the new system, introduces increased potential for design or operational problems resulting from error, as well as possible shortcuts on acceptance criteria. ~ The primary advantages identified in order of decreasing importance are as follows: 1. As currently planned, the addition of the alternate RHR, brings a new piping connection point to the primary system outside of the high radiation area. This connection point can be used for possible future primary coolant system additions or improvements that may be deemed necessary. i 2. The addition of an alternate RHR provides one more backup cooling system j that could be used if needed. i I 3. The alternate RHR system, as currently configured, has a minimum number of valves and better instrumentation for monitoring system performance than the existing system. This should minimize the potential operational problems. 4. The alternate RHR system, as currently configured, is outside the auxiliary building and would thus be more accessible for routine maintenance and surveillance. DISCUSSION OF RISKS AND ADVANTAGES Primary Risks Se view as the major cor.cern the risks associated with bringing the primary coolant outside both the containment and the auxiliary building into the proposed temporary housina, " quonset hut." The proposed structure is of questionable integrity both from a radiation leakage concern and from ability to withstand unexpected (yet possible) external loadings; e.g., plane crash, truck or other site equipment. Bringing the high activity primary coolant into such a building n eC

W Primary Risks (Cont.) Page 4 outside the containment definitely reduces the barrier to fission product activity release to the environment, and thus reduces substantially the effectiveness of the overall system in containing the activity. In our view, this is the most important risk associated with the current plan. A corallary to this primary risk is that operation of the alternate system in the temporary housing will significantly increase the risk of exposing site workers to unacceptably high radiation doses. This risk would likely result in some impact on the on-going site recovery activity on the island; i.e., it adds additional risk and restriction to an already highly constrLined activity. This risk is considered to be a close second in importance relative the primary risk above. The third risk identified, as with the second, ranks high in importance. Cutting into and cpening the auxiliary building for the duration of the work breaches the final outermost barrier for external rad Lion release, abeit for a short' while. Unless a permanent structure of equivalent integrity; e.g., structural, leak-tightness, and external access provision, is first built around the intended cut in the auxiliary building wall and sealed off, prior to the cut there is a very undesirable reduction in the barrier to activity release. Secondary Risks. The next most significant risk identified is that there will be a time period when both existing RHR systems will be unavailable for any service while the decay heat suction line is being cut into and then the new piping closure is made. There is also a radiation exposure risk associated with this operation for both suction and discharge pipe cuts and reclosures, which is particularly uncertain because of the unknown leakage via the existing isolation valves. This risk is considered secondary to the first three identified and is,not of j suf !cient concern to argue against adding the new piping connection. However, it is a risk which can affect the schedule and progress of this activity. i There is an additional risk of increased contamination of portions of the existing RHR system; i.e., discharge piping downstream of the RHR heat exchagers, and suction piping upstream of the RHR pumps, if the alternate RHR system were used first. This is a secondary risk, but should be kept in mind since one of the reasons for going to an alternate RHR system was to apparently keep from crapping up the existing RHR and auxf Tiary building if at all possible for future availability during clean-up operations. The final risk identified was that the accelerated schedule for design and fabrication introduces opportunity for future design and operational problems due to errors and/or shortcuts on acceptance criteria. Actually, although this risk exists, it appears that precautions are being taken to assure that errors are avoided and that all normal design and licensing criteria are satisfied. There appears to be significant review by Westinghouse and the NRC, normal quality assurance requirements are being applied and industry code criteria and documentation requirements are being followed. 165 256

/ Secondary Risks (Cont.) Page 5 One important additional action which should, however, be taken is to involve B&W engineers early in the design review process for the alternate system as well as for the design of any improvements planned for the existing RHR system. Advantages In our review, the most important advantage of the planned addition of an alternate RHR is that it creates a new piping connector point to the primary system outside of the high radiation. This connection point, whether it is used at this time or not provides the flexibility for numerous possible future actions that may be desired; i.e. decontamination provision, methods for improved core cooling, etc. This may prove very useful and is a good insurance policy against potential future problems with operation in the cooled-down mode. The obvious additional a ivantage is that one more alternate backup cooling system would be available if ever needed. While it is not currently intended for use unless necessary, if it were provided in an adequately designed structure, it would provide additional assurance of long-term safety. There appears also to be an advantage to the alternate system in that it is designeo to perform only one function, and as a consequence, has a minimum of. unncessary frills; e.g., a minimum number of valves. Also, the alternate system appears to have more complete instrumantation for monitoring operational performance. The final advantage identified in this review is that the alternate RHR system, as currently configured outside the auxiliary building, would be more acca-.51e for routine maintenance and surveillance. This is an obvious aovantage w. 5 would make it more desirable as a long-term cooling system if one were ne?ded. 165 257

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