ML20041D849
| ML20041D849 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 03/04/1982 |
| From: | Walbridge W SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.1, TASK-TM TAC-44402, NUDOCS 8203090330 | |
| Download: ML20041D849 (14) | |
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e snuo SACRAMENTO MUNICIPAL UTILITY DISTRICT O 62o1 S Street. Box 15830, Sacramento, California 95813; (916) 452 3211 March 4, 1982 I
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!:.x DIRECTOR OF NUCLEAR REACTOR REGULATION
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-3 ATTENTION JOHN F STOLZ CHIEF h
/go 4 * *. m,."T"N OPERATING REACTORS BRANCH N0 4 6
U S NUCLEAR REGULATORY COMMISSION WASHINGTON D C 20555 h
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DOCKET 50-312 RANCHO SEC0 NUCLEAR GENERATING STATION UNIT N0 1 NUREG-0737, ITEM II.B.1 - REACTOR COOLANT SYSTEM (RCS) VENTS Our letter dated July 1,1981 provided information for the TMI Action Plan, NUREG-0737.
Your letter dated January 18, 1982 requested additional informa-tion in order to complete your review. The attachment to this letter provides the requested information.
If we can provide any additional information on these items, please advise.
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~, un ' p Wm. C. Walbridge General Manager Enclosures O /( 8203090330 920304 PDR ADOCK 05000312 P PDR As rircreic s y ". t r a s i r v.t s, veut r ;i A s t o o. r-is 'ut u t s i< ! or cat #iorsia
ENCLOSURE Requested Information on Reactor Coolant System (RCS) Vents Reference 1: Generic Operating Guidelines for High Point Vents Reference 2: NUREG-0737 l.a. The decision to terminate venting would be based on the 3.5 volume percent hydrogen concentration control limit in the containment building, which is discussed in appendix 14.C of the Rancho Seco FSAR. The pressurizer vent would also be closed when the water level in the pressurizer reached the upper limit. 1.b. The determination of whether a bubble in the primary system is mainly composed of noncondensable gas or of steam is not of particular significance. Either type lof bubble can hinder the reestablishment of or interrupt natural-circulation cooling if the bubble becomes too large. However, the composition of the bubble can be inferred from the type of transient which occurs. If the transient progresses to an inadequate core cooling (ICC) situation, then noncondensable gases will probably be contained in the bubble. For plant transients in which a bubble develops in the RCS and plant parameters indicate the core is being cooled, the bubble will primarily be composed of steam. The determination of the location and size of a bubble can be made by monitoring plant process parameters, mainly primary and secondary system temperatures and pressures, during the transient. If a bubble develops in the hot leg of such a size as to decouple the primary and secondary 4 i f 1 e y sw 7
systems, thereby initiating an interruption of heat removal via the~ steam generator, the operator is directed to bump the pumps and/or use the high point vents to remove the bubble and reestablish natural circulation. Decoupling of the steam generator is noted by the difference in temperature between the cold leg RTD and the steam generator saturation temperature. In addition, the steam generator pressure will decrease and, for small breaks wherein the steam generators play an active role, the primary side pressure will increase. The decoupling can be further confirmed by depressurizing the steam generator and noting no accompanying change in the primary system. Following the removal of the bubble in the hot leg and the establishment of natural circulation, the operator is expected to be able to recognize a reactor vessel head bubble by monitoring pressurizer spray effects on pressurizer level. Methods for removal of a bubble in the reactor vessel head are provided in Section 3.2 and 3.3 of Reference 1. l.c. The use of the PORV in conjunction with HPI for depressurization and volume control for transients wherein the steam generator heat sink is not available is being incorporated into AT0G. i 2. For the SBLOCA cases wherein the steam generators play an active role in t removing a portion of the core decay heat, the high points vents can be utilized, if the RC pumps are not available, to remove trapped gases in the hot leg and to return the primary system to subcooled natural circulation. In examining the usage of the vents, as documented in Reference 1, it was found that the period of the transient for which the utilization of the vents will be most effective is the refill period. As discussed on Page 8 of Reference 1, during the refill period of the transient, the level in the primary system will rise above the elevation 1 i.-
of the auxiliary feedwater inlet nozzle. This will result in a cessation of the boiler-condensor (steam condensing) heat transfer mode. Since the SG will cease to be an effective heat sink for the primary system, the RCS pressure will increase, thereby indicating a "decoupling" of the primary and secondary systems. Timely operation of the vents is assured in the following manner. Fi rs t, vent operation is initiated only on a recognized need, i.e., lack of primary and secondary system coupling. Second, vent operation, once instigated, is continued until subcooled natural circulation is established. Subcooled natural circulation can be determined from system parameter displays and is measurably different from two phase natural circulation or boiler _condensor by the subcooled nature of the hot leg temperature. The slight excess discharge of inventory through the vents, caused by leaving the vents open until acceptable subcooling is reached, is necessary to assure full development of the desired cooling mode. This excess discharge does not pose significant adverse consequences as a leak already exists elsewhere in the system. In this situation, timely operation of the vents means positive assurance that, following the initiation of the refill mode, the transition to solid natural circulation is permanent. The operator, in fact, can't determine whether the plant is in the two-phase natural circulation cooling mode or the boiler-condensor mode of operation. However, as long as coupling is maintained, the operator-can initiate the cooldown with the steam generator. The operator will be able to determine if decoupling occurs as described earlier. The operator will then reestablish natural circulation by bumping the pumps as the preferred method and/or using the high point vents if pumps are not available.,
The detailed, explicit operator guidelines for utilizing the HPVs are being developed at this time. These guidelines will be created in the AT0G format for future inclusion into AT0G procedures. '3. Section 3.3 of Reference 1 describes the removal of noncondensable gases or steam in the reactor vessel. head for plants without reactor vessel head vents. The depressurization rates shown in Figure 2 of Reference 1 are not based on computer analyses. The curves were developed using hand calculations as follows: It was assumed that the plant is in subcooled natural circulation with the reactor vessel head filled with hydrogen down to the outlet nozzles. At any given pressure the volumetric capability 3 (ft /sec) of the high point vents to remove the hydrogen gas can be calculated. This sets the allowed expansion rate of the hydrogen gas in the reactor vessel head to the hot leg. The ideal gas law was then utilized to translate the gas expansion rate into the maximum allowable depressurization rate which assures natural circulation would not be interrupted. The depressurization rates of the PORV and pressurizer vent, if installed, were calculated based upon a steam discharge. It should be noted that the expanding hydrogen gas bubble in the reactor vessel head is assumed to accumulate only in the hot leg high point vent region and none of the gas goes to the pressurizer. This leads to the worst case noncondensable gas accumulation rate in the high points of the hot leg. Thus, if the depressurization rate is controlled within the maximum rate then natural circulation should not be interrupted. If. natural circulation is interrupted during the venting of the vessel head the operator is instructed to stop the depressurization and to re-vent the hot leg to reestablish natural circulation. Since core cooling would be maintained even with an interruption in natural circulation, the effect of loosing natural circulation moinentarily has little safety significance. __
The hand calculations described above are for a noncondensable gas bubble in the reactor vessel head.as opposed to a steam bubble. Since the hot legs will be significantly subcooled relative to the _ reactor vessel head (50 F), any steam entering the hot leg from the reactor vessel head area would be condensed. In addition, if the subcooled margin is lost, the depressurization will be stopped until adequate subcooled margin is restored. Thus, the above described procedure _is equally effective for a steam bubble in the reactor vessel head. 4. It is possible to have a slug of water at the reactor vessel high point vent. It is not as likely to have a slug of water at the hot leg high point vent but nothing can preclude.that condition. The vent valves do-not have specific analyses on them to demonstrate that a slug of water impacting the nozzle of the vent itself while open would be able to withstand the dynamic loads associated with the impact. However, the dynamic load would be distributed throughout the venting and piping structure. The dynamic load should be considered for each vent mechanical and structural design including location of supports on the piping. T 5. In this case, where the plant is in the shutdown cooling mode and water has flashed to steam in the hot leg during depressurization, there is no problem of any safety significance. This condition would be noted by a rise in the pressurizer level and a subsequent loss of subcooling margin. 4 If all other plant process instrumentation and incore instrumentation is normal relative to the shutdown cooling made, the operator would limit the cooldown rate by procedures already in place until he demonstrates the pressurizer is the controlling pressure element in the primary system. The operator is not directed to use the high point vents for the condition described above. Unless deteriorating conditions in the primary system were indicated, the use of HPVs during these. circumstances is not needed.._.
M ' .E.,. j In the event that a plant were to make use of the vents during the condition described above, it would be left up to each plant to control I via administrative procedures, or.otherwise, to limit venting in containment while personnel were present. If personnel were in containment AND a bubble was determined to be present in the hot leg during the shutdown cooling mode, there is no reason to startle or alert personnel unnecessarily. Reestablishing the pressurizer as the primary system pressure controlling element doesn't require breaching primary integri ty. If primary conditions deteriorate and the use of the vents'is desired, it would be prudent to clear containment and take other necessary. actions to maintain the integrity of the containment prior to their use. 6. The long term cooling requirement of 10CFR50.46(b)(5) does not specify the reestablishment of single phase natural circulation as a design objective. Rather, it states that the... " core temperatures shall be maintained at an acceptable low value and decay heat shall be removed for the extended i period of time required by the long-lived radioactivity remaining in the core." The long term cooling of the core, as required by 10CFR50.46(b)(5), is provided by assuring that.the core remains covered by a two-phase mixture. To assure this capability in the long term, the high pressure injection has been designed to take suction from the reactor building sump, thereby assuring an indefinite supply of coolant. The i SBLOCA evaluations demonstrate that the ECC systems satisfy this requi rement. It has never been assumed that single phase natural circulation would be reestablished following design basis SBLOCAs. l l l r .,... ~.
Operation of the RC pumps ano/or the high point vents is believed necessary in order to reestablish single phase natural circulation during certain small breaks. The range of break sizes, for which the reestablishment of single natural circulation would aid in bringing the plant to cold shutdown, is bounded by the largest break size for which 2 natural circulation would not be lost (approx. 0.005 ft ) and the smallest break size for which the RCS pressure spontaneously depressurizes 2 to the LPI setpoint (approx. 0.05 ft ). For breaks'which are isolated during the period between the interruption of natural circulation and start of steam condensing heat transfer, the RC pumps and/or vents may be used to reestablish single phase natural circulation. Hcwever, if the steam bubble in the hot leg U-bend is small, it may be possible to reestablish natural circulation by pressurizing the system with the HPI. Alternatively, the plant would evolve to a high pressure and displace sufficient inventory through the PORV or code safety valves to establish boiler condensor heat removal. Although the RC pumps and high point vents may be required for the establishment of single phase natural circulation, the long term cooling requirement of 10 CFR 50.46(b)(5) is met without utilizing the RC pumps or the high point vents. The present SBLOCA transients have been analyzed past the point at which the primary system pressure is controlled by the break, at pressures below the SG secondary pressure, or by the steam generator in a boiler-condensor mode of cooling; the core has been recooled; and the ECC injection exceeds the core boiloff. Since the core l l l l l I
$ = *~ decay heat continues to decrease thereafter, the ECC systems are thus assured of providing adequate makeup to keep the core covered provided that primary system pressure can be controlled. Pressure control is provided by the break, for the larger SBLOCAs, and by use of the steam generator for the smaller breaks. Since the condensing surface in the SG is located at an elevation above the top of the core, primary system pressure will be controlled at a value which assures that the HPI will keep the core covered for the long term. Additionally, since the HPI and LPI system can be operated from the containment sump, following the emptying of the BWST, long term ECC injection is assured. As seen from the foregoing discussions, long term cooling of the core for a SBLOCA is maintained without the need to establish single phase natural circulation. Thus, the RC pumps and the high point vents are not required to be part of the engineered safety features. It is our belief that the use of available plant equipment, whether or not it is " safety grade", which aids the operator in managing the plant during a transient or accident should be identified in the operator guidelines. Thus, the i operator guidelines do contain instructions for utilizing the RC pumps and the high point vents for the purpose of returning the plant to single phase natural circulation. l l i l l l l l l l
7.a. All piping, valves and components of each RCS vent line have been designed'to the standards required by ASME Section III Class 1. The piping, valves and components of each vent line will be i Seismic Category 1 and Quality Class 1. Compliance with these design requirements will be verified prior to the installation of any component, b. The materials used in fabricating the components of the Reactor Coolant System Vents are consistent with the material selection for the Reactor Coolant system as indicated in section'4.3.2 of the FSAR..The material selected, types 304 and 316 stainless steel, will be fabricated and tested in accordance with S.R.P. section 5.2.3. This ASME section III, Class 1 material will' have all documentation verified prior to its installation. c. RCS vent lines are separated from each other by physical barriers. The steam generators and their associated high point vents are enclosed by the secondary shield walls. -The secondary shield walls extend up above each vent line to ensure that any postulated missile or pipe rupture could not affect more than one high point-vent. Therefore, at all times there are at least two vent paths that will remain functional., ,-e
8. Each RCS vent line will direct its respective discharge into a clear area where there are no nearby structures, systems and components essential to a safe reactor shutdown or mitigation of the consequences of a design basis accident. To further reduce the effects of impingement, each RCS vent line will have a sparger to disburse the effluent stream. The as built vent discharge area will be reviewed prior to installing any vent line to ' verify that it meets the above reouirements (see - attachedsketches). 9.a. All components in each RCS vent line and the supports are designed to Seismic Category 1. This design ensures that each vent line will be able to withstand a safe shutdown earthquake. b. The only postulated missiles are vent valve stems from each vent line. Each valve is oriented in its upright position; therefore, the postulated missile would have an upward trajectory, away from any safety related equipment. Further, the valves intended for this service are of the backseat design or are otherwise. enclosed and therefore these components are not considered missile hazzards, c. Since the Rancho Seco RCS high point vent lines are 1" or less in diameter, the fluid spray from the failure of a pressurized portion of the line is not required to be analyzed per Branch Technical Position ASB 3-1..
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