ML20039H207
| ML20039H207 | |
| Person / Time | |
|---|---|
| Site: | 05000561 |
| Issue date: | 12/20/1976 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML111090060 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8201190720 | |
| Download: ML20039H207 (13) | |
Text
{{#Wiki_filter:_ - _ _ _ _ _ - l Auxiliary and Power Conversion Systems Branch Safety Evaluation Report Babcock G Wilcox Standard Nuclear Steam System (B-SAR-205) PSAR Docket No. 50-561 J 3.4 Water Level (Flood) Pr_otection Design provisions for protection of B-SAR-205 systems against the effects of floods will be discussed in the Utility / Applicant balance-of-plant design application. } B6W has included an interface requirement that the location, arrange-ment, and installation of safety related systems and components shall i be such that the effects of floods will not prevent these systems and components from performing their safety function. We conclude B-SAR-205 provides the necessary interface information, and therefore, is acceptable. This section will be evaluated in applications re-l i ferencing B-SAR-205. 3.5 Protection Against Internally Generated Missiles _ (Outside Containment) BSW has stated that their equipment must be protected from the impact of postulated missiles and have provided a tabulation of portions of the NSSS system which must be protected from internally generated 4 missiles outside containment. ( This protection will be provided by applicants referencing B-SAR-205. We have reviewed the tabulation of equipment to be protected from in-ternally generated missiles and find it includes all the safety 8201190720 010403 PDR FOIA MADDEN 80-515 PDR
2 3.5 related equipment and is acceptable. Protection against internally generated missiles (outside containment) will be evaluated in appli-cations referencing B-SAR-205. 3.6 Plant Design for Protection Against Postulated Piping Failures in Fluid Systems Outside Containment BGW has provided a tabulation.of.those portions of safety-related systems and equipment outside containment, within the scope of B-SAR-205 that must.be protected from piping failures. BGW has stated that the layout and pipe break analysis for B-SAR-205 f systems outside containment will be provided by the Utility / Applicant as part of the balance-of-plant design. The review of the implementation of Branch Technical Position APCSB 3-1, " Protection Against Postulated i j Pipe Failures in Fluid Systems Outside Containment" will be performed I inapplicationsreferencingBfSAR-205duringthesafetyreview. l l 5.5.11 Pressurizer Relief Tank i The pressurizer relief tank (BGW reactor coolant drain tank) will be supplied-by the Utility / Applicant in the balance-of-plant i design. BGW has provided interface criteria which we consider acceptable for the applicant to design a pressurizer relief tank and piping system to enable the NSS system to perform its intended function. The pressurizer relief tank system is not a safety-related system and is not required for safe reactor shutdown.
3 5.5.11 This section will be evaluated in applications which reference B-SAR-205. 9.0 Auxiliary Systems The auxiliary systems supplied in B-SAR-205 include: new fuel storage racks, spent fuel storage racks, fuel handling system and chemical and volume control systems. We have reviewed these systems with regard to their design bases and criteria. i -{ The evaluation also includes the;B5W interface requirements for the t design of the following safety-related auxiliary systems and other auxiliary systems that will be supplied by the Utility / Applicant as part of the balance-of-plant design. The safety-related systems are: station service water system; component cooling water system; j i ultimate heat sink; heating, air conditioning and ventilation systems; h and auxiliary feedwater-system. The other auxiliary systems are: pressurizer relief tank; demineralized water system; compressed air l system; and fire protection system. 9.1 Fuel Storage and Handling 9.1.1 New Fuel Storage Racks j B SW is responsible for the new fuel racks for B-SAR-205 and the necessary interface requirements imposed on the designer of the new fuel storage facilities. The new fuel racks have a storage capacity for one-third of a core (72 fuel assemblies). The new fuel racks will be designed to seismic Category I requirements.
4 1 1 9.1.1 The new fuel storage racks will consist of an array of rectangular xb, d storage tubes (structurally reinforced) having a nominal center-to- ) h center spacing of 21 inches. This center-to-center spacing is sufficient to maintain K,ff of 0.95 or less including the higher anticipated enrichment and assuming flooded unborated water. Further-more, the design of the.new fuel storage racks is such that the K,ff will not exceed 0.98 assuming optimum moderation. ~ BSW has not provided all the necessary interface information for the new fuel racks, i.e., rack dry and loaded weight, rack wall tie and foot interface information. BGW has committed to provide this interface information. l [We have evaluated the proposed design of the new fuel storage racks and conclude that they meet the applicable positions set forth in t Regulatory Guide l.13 and the requirements. of General Design Criterion 62. We will require the applicant to provide the necessary interface information.] l The new fuel storage facilities will be evaluated in applications i referencing B-SAR-205. 9.1.2 Spent Fuel Storage Racks BGW is responsible for the spent fuel racks for B-SAR-205 and the necessary interface requirements imposed on the designer of the spent fuel storage-facilities. The spent fuel storage racks have a l
j 5 9.1.2 storage capacity of one and one-third cores (288 fuel assemblies). The spent fuel storage racks will be designed to seismic Category I requirements. The spent fuel storage racks will consist of an array of rectangular storage tubes (structurally reinforced) having a nominal center-to-center spacing of 13.0 inches. This center-to-center spacing is sufficient to maintain K of 0.95 or less including the highest ff anticipated enrichment, and assuming unborated water. BGW has not provided all the necessary interface information for the spent fuel storage racks, i.e., dry and loaded weight, rack wall tie; i and foot interface information. = B6W has committed to provide this interface information in a later amendment. Until BGW furnishes the required information this will remain an open issue. [We have evaluated the proposed design of the spent fuel storage f racks and conclude that they meet the applicable positions set forth in Regulatory Guide 1.13 and the requirement of General Design j Criterion 62. We will require the applicant to provide the necessary i interface information.] The spent fuel storage pool facilities will be evaluated in appli. cations referencing B-SAR-205.
6 f 9.1.3 Spent Fuel Pool Cooling and Cleanup System The spent fuel pool cooling and cleanup system will be designed and provided by the Utility / Applicant as part of the balance-of-plant design. B 6W has provided interface requirements, including heat loads, minimum water depth over spent fuel, and other information to' enable the Utility / Applicant to design a suitable spent fuel pool cooling system. We have reviewed the information provided by B5W and conclude it is acceptable. The spent fuel pool cooling and cleanup system will be evaluated in applications referencing B-SAR-205. } 9.1.4 Fuel llandling System i The fuel handling system will be an integrated system of equipment, tools, and procedures for refueling the reactor, The system will i provide for hindling and storage of fuel assemblies froin receipt of l l new fuel to the shipping of spent fuel. The new fuel handling crane, l spent fuel cask, overhead handling crane, and facilities designs will be provided by applicants referencing B-SAR-205. The fuel handling system within the scope of the B-SAR-205 will include new fuel handling machinery and special tools designed for underwater handling of spent fuel from the time it leaves the reactor until it is placed in a cask for shipment from the site.
7 i j 9.1.4 The fuel handling system will be designed such that in the event . j I of a safe shutdown earthquake the equipment will not fail in a i manner which would affect safety-related equipment. We have reviewed the fuel handling system design and interface requirements and conclude that the proposed fuel handling system in B-SAR-205 scope meets.our design -criteria, and therefore, is acceptable. The portion of the fuel handling system supplied by. Utility / Applicants will be evaluated in applications referencing B-SAR-205. l 9.2 Water Systems 9.2.1 Service Water System and Ultimate Heat Sink 9.2.5 [BSW has provided the NSSS heat loads that must be transferred from the component cooling water system to the service water system and to.the ultimate. heat-sink. We have reviewed the NSSS heat loads and conclude that the interface data beginning at 6 hou'rs up to 30 days after reactor shutdown is acceptable. However, we will require i similar interface data for the first 6 hours. The complete data l is required to enable Utility / Applicants referencing B-SAR-205 to design an acceptable service water system and ultimate heat sink. l B6W has committed to provide -this additional information in a later amendment. These systems will be evaluted in applications which reference B-SAR-205.] l
B l 9.2.2 _ Component Cooling Water System (CCW) }g The component cooling water system will provide cooling water to / : dissipate heat from various B-SAR-205 components for both normal and 4 i post-accident operation. The component cooling. water system will be provided by the applicant as part of the balance-of-plant design. 1 The major equipment that is considered to be part of the basic ~ B-SAR-205 plant and to be cooled by component cooling water are: i reactor coolant pumps (4), decay heat removal coolers (2), decay heat removal pumps (2), the letEown coolers (2), sample coolers and RCP seal return coolers (2), makeup pumps (3), reactor coolant bleed j evaporators (2), degassifier and control rod drive mechanisms (CRDMs). I I ) B5W has identified interfaces for all safety related components within the scope of B-SAR-205 that use CCW. The interfaces are identified by pressure,-temperature, heat transfer, flow requirements I and the quality group and seismic classification for the B-SAR-205 \\ b l equipment at each physical interface connection. l l We have reviewed the interface requirements in B-SAR-205 and conclude j I ' < ( ] that BGW has supplied adequate interface information for a Utility / { ) { Applicant referencing B-SAR-205 to design a satisfactory component i cooling water system. The component cooling water system will be- ^- reviewed in applications referencing B-SAR-205. f 9.2.3 Demineralized Water Makeup System s The demineralized water makeup system will be designed and provided by the Utility / Applicant in the balance-of-plant design. of' e
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9.2.3 B5W has provided interface criteria which we consider acceptable for t. the applicant to design a demineralized water makeup system to enable i .the NSSS system to. perform its. intended. function. The demineralized e water makeup system is not a safety-related system and is not required for safe reactor shutdown. .( This system will be evaluated in applications which reference B-SAR-205. f 9.3 Process Auxiliaries i J 9.3.1 Compressed Air System The compressed' air system ~will be designed and provided by the Utility / Applicant as part of the balance-of-plant design. 1 4 1 \\ BSW has provided the interface infonmation.to enable the Utility / i Applicant to design a suitable compressed air system to m'eet the requirements of B-SAR-205 design scope. We have reviewed the inter-face information provided by BGW and conclude it is adequate, and therefore acceptable. The compressed air system will be evaluated in applications referencing B-SAR-205. l l l
f-10 4 9.3.4 Chemical and Volume Control System y The chemical and volume control system (CVCS) consists of the make-up and. purification system.and the chemical addition and boron re-i covery system. The CVCS will be designed to control and maintain reactor coolant inventory; to control the boron concentration in the reactor coolant through the process of makeup and letdown and provides seal water injection to the RC pump. CVCS purifies the letdown fluid by demin-eralization. Portions of this system also supply high pressure in-jection of borated water into the reactor coolant system for emergency boration. The boron recovery system recovers boric acid from the i reactor coolant for reuse, t i Portions of the CVCS required for safe shutdown of the reactor will f be designed'to seismic Category I requirements. i I j The Utility / Applicant is required to provide component cooling water in the range from 70 F to 105 F to the letdown coolers, and the reactor coolant pumps seal return ?olers for normal operation and no greater than 120 F for cooldown and accident conditions. The l j , Utility / Applicant must also provide the capability for maintaining a temperature of at least 70 F for all portions of the CVCS system J' ~ containing concentrated boric acid solution to prevent precipitation ^ i - of boron. k s[ t t f _' ' ,~ l a
4 i 11 i 4 o 9.3.4 We have reviewed the adequacy of the B-SAR-205 proposed design 7 .t 1 - j criteria and design bases for performing the necessary functions j ~i + of the CVCS during normal, abnormal, and accident conditions. We ] have concludalthat the design criteria and design bases and interface -i t requirements are in conformance with the General Design Criteria l and are, therefore, acceptable. t 1 9.4 Heating, Ventilation and Air Conditioning Systems The heating, ventilation and air conditiong (HVAC) systems required for essential and non-essential areas outside containment will be designed and provided by the Utility / Applicant as part of the j balance-of-plant design. I O i B5W has provided the range of temperature and humidity design inter-4 [ face requirements for areas housing safety related equipment fur-nished as part of B-SAR-205 design scope. We have reviewed the B5W interface requirements and information provided for the HVAC l systems and conclude they are acceptable and that sufficient in-t l formation has been provided in B-SAR-205 to permit a Utility / Applicant l to design satisfactory HVAC systems for the balance-of-plant. The i HVAC systems will be evaluated in applications referencing B-SAR-205.
i 12 9.5.1 Fire Protection System [The fire protection system will be designed and provided by the . Utility / Applicant as part of the balance-of-plant design. B6W is being requested to re-evaluate the fire protection system interface requirements and criteria and to identify B-SAR-205 equip-ment containing combustible material in conformance with Branch Technical Position APCSB 9.5-1, " Guidelines for Fire Protection i for Nuclear Power Plants." We will evaluate this information in a supplement to this report. f The fire protection system will be evaluated in applications referencing B-SAR-205.] } l 10.0 Steam and Power Conversion System i BGW has provided two once through steam generators for steam con-I t version which removes the heat from four reactor coolant loops. l l The B-SAR-205 scope ends at the steam generator feedwater inlet and steam outlet nozzles. W e have reviewed B-SAR-205 interface requirements and information provided for the steam and power conversion systems and conclude that sufficient information has been provided to permit a Utility / Applicant to design satisfactory systems for the balance-of-plant design and, therefore, is acceptable. The steam and power con-version system will be evaluated in applications referencing B-SAR-205.
h 13 j f 10.4.1 Auxiliary Feedwater System s The auxiliary feedwater system (AFWS) is an engineered safety feature that will be designed and provided by the Utility / Applicant refer-i encing B-SAR-205. i B6W has provided interface requirements, i.e., system flow rates, t pressure, temperature, initiation time and other pertinent infor-mation regarding AFWS. W e have reviewed the information provided by B6W and conclude the necessary interface requirements have been provided that will enable a Utility / Applicant referencing B-SAR-205 to design an acceptable i ' AFWS; --This system will be evaluated in applications referencing B-SAR-205. 4 We are currently evaluating design and operating conditions that could result in damage to feedwater system piping as a consequence e, of feedwater flow instability occurrgnces such as that at Indian Point Unit No. 2 on November 13, 1973. The results of this in-vestigation may result in further requirements being imposed upon B-SAR-205 so that unacceptable damage will not result from feed-water hammer. k ..,,.. - - -}}