ML20058K867
| ML20058K867 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 03/12/1973 |
| From: | James D NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20058K866 | List: |
| References | |
| NUDOCS 9104250464 | |
| Download: ML20058K867 (26) | |
Text
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NORTHERN STATES POWER COMPANY Minneapolis, Minnesota REPORT ON TORUS TO DRYWELL l
VACUUM BREAKERS !
TESTS AND MODIFICATIONS FOR l MONTICELID NUCLEAR GENERATING PIANT l
l Prepared by:
D W James March 12, 1973 g 76 ***" e. .mmr pp.
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- l TABIZ OF COIrfEIfPS i l
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i I. System Description 1 j II. Summnry of December 15, 1972 Findings and Results 2 III. Vacuum Breaker Modifications 4 A. Improvement of Valve Closing Stroke to Provide Further 4 Assurance of Proper Seating !
B. Replacement of Snap Lock Limit Switches with Micro 5 i Switches to Improve Position Indication 3
C. Upgrading of Corrosion Pesistance of the Air Operators 6 j to Further Ensure Testability l D. Surveillance Following the Modifications 7
- 1. Preoperational Tests 7
- 2. Exercise Testing 7 3 Routine Icak Test 7 IV. Safety Considerations 8 A. Leakage Limits B B. Flow Considerations 13
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V. Technical Specification Considerations 13 1
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- NORTHERN STATES POWER COMPANY
, MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 LICENSE NO. DPR-22 REPORT ON TORUS 'IO-DRNELL VACUUM BREAKERS 1
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f The following information has been prepared in response to an AEC letter, dated January 12, 1973, requesting infomation on the subject vacuum breakers.
! I. System Ibscription i The wetvell/dryvell vacuum relief system includes ten (10), eighteen-inch 3
vacuum relief valves. The valves are located as follows: one vacuum breaker installed at each of six vent-to-vent header positions and two vacuum breakers installed at each of the remaining two vent-to-vent header ;
positions. Se design actuation set point is 0 5 psi for full open. Based on the estimated closing moment at full open, however, the actual actuation set point is less than 0 3 psi. Operability of the vacuum breakers is de-termined through the use of a test air operator. he operator is provided to open the valves remotely. Redundant indicator lights are provided to note the open and closed positions.
4 The vacuum breakers instaned at knticello are manufactured by Atwood and
! Marrill Co. Se valve flange rating is 150 lbs. Se position switches are l
snap lock limit switches, Model-fS12-67 and #SL2C-67, manufactured by the National Acme Company. Figure 1 shows the vacuum breaker as installed at
! Ibnticello. The test air operator and position switch configuration, as-1 vell as a list of materials are shown in this drawing. he present vacuum 2
breaker position indication provides local and remote indication of valve j position at indication / test panel C04 in the control room and at a panel located at the 935' level of the northeast portion of the reactor building. .
j Both panel indications are powered fmm the same power supply and the same breakers, Y2O circuit 1. The redunannt snap lock switches actuated by a j shaft mounted cam provide the means of detecting valve position.
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! The materials were designed for the following conditions:
1, a. Normal Operation 2 psig, 30-1500F, 100% RH Drywell:
Suppression Chamber: 2 psig, 50-1500F, 100% RH
- b. Transient Accident Drywell: 57 psig, 2810F Suppression Chamber: 35 psig, 1800F 1
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- c. Radiationenvironmentvillbe300 mrem /hr l t
- d. Iovest service metal temperature is 300F 1 he valve bodies are AS'IM A-352 GRLCB and meet the impacttest requirements !
of ASME Code Section III, Paragraph N-1210. The disc is cast aluminum.- he j 1
valves were subjected to a 225 psig bydrostatic test. Certified copies of.
all mill certificates are available.. j te suppression chamber coating is Carbo-Zine 11 primer and phenoline-368 i finish. Carbo-Zine n was also used to coat the carbon steel and cast j iron surfaces of the valve. j here should be no deleterious effects on the valve materials from the coat-ing or the nitrogen atmosphere. l here has been no test performed on the valve or the position indicators in j a simulated accident environment.
The only material that is not completely suited for this environment is the-teflon packing. Teflon vin begin out-gassing fluorine at about 1.0 x 100 R 'Ibtal time integrated dose over a 40 year design life vill be ap-proximately 9 3 x 10+4R, based on an exposure ate of 300 mrem /hr. Bis is l not considered an immediate problem due to the- relatively small exposure so i far received and for reasons discussed later in this report.
Both the preoperation and periodic surveillance tests included essentially only a functional check of the air operator and position indicators. The i only acceptance requirement--is that the valve is verified, by %dicating i lights, to close. Be required surveillance frequency is once per opera- i i ting cycle. Although there have been no regularly scheduled surveillance i tests to date, special tests have been conducted on a number of occasions.
The torus vacuum breakers were exercised weekly during startup to monitor j effects of a humid environment. No problems were reported.' Exercise tests vere conducted on several occasions when it was detemined to be appropriate I l by the plant staff. In November of 1971, it was discovered that the line l supplying air to one of the air operators on a vacuum b m aker valve was damaged by movement of the torus baffles. Repairs were made and an exercise i test was conducted during startup on January 19, 1972. No si6nificant prob- ,
lems were discovered until December 15, 1972 when an exercise test was con- l ducted in conjunction with an inspection because of reports of problems at l
. Quad Cities. Results of that inspection are discussed in the following section.
II. Summary of December 15, 1972 Findings and Results
,. Due to recent torus-to-dryvell vacuum breaker. problems experienced at other j operating nuclear plants, it was decided to inspect the E ntice11o torus-to-I l
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i dryvell vacuum breakers for proper operation. This inspection was perfomed
! during a scheduled maintenance shutdown on December 15, 1972. One of the i i ten vacurm breakers was found to be approximately 11/4 inches open; however, l 1 the position indicating lights indicated that this valve was closed. During j the inspection, an exercise test was performed and four of the vacuum breakers !
j did not close fully. In addition, two of the test operators did not operate 3 properly. j j
l l Manual exercising of the valves indicated excessive friction between the ]
I shaft and shaft packing. 1he valves are constructed with a close tolerance J l teflon bushing on each end of the shaft with several rings of teflon pack- 1 i ing outboard of the bushing. All of the teflon packing was removed. It-is l
] not expected ' hat the teflon packing vill be replaced, however, a substitute i shaft ae?. ling method proposed by Atwood and Morrill is being investigated
, for use at Monticello. With the packing removed, all the vacuum breakers j vere leah tested by. establishing a .5 psi differential pressure between the dryvell and torus and surveying for leaks with a sonic probe. No sig-l 2ificant shaft leakage could be detected. Some minor seat leakage was detected and as a result, the valve seating surfaces were cleaned and the j metal areas were dressed up with emery cloth.
Two exercise air operators required cleaning and replacement of the actua-q tor piston sealing rings. Following these repairs, the operators functioned g properly.
Prior to reinerting the primary containment on December 20, 1973 each of the
, ten torus-to-dryvell vacuum breakers was mannally lifted 1/2 inch off its i seat and released. Allvalvesclosedfullyfromthis1/2inchopenposition.
] V.lve exercising with the air operators also resulted in free operation in toth directions. )
i In addition, a leak rate test was conducted to determine the amount of leak-l age through the vacuum breakers. This test was conducted by pressurizing the dryvell to approximately 7 inches of water above that of the torus and observing the pressure decay. A leakage rate of approximately 18 SCPM was measured. An inspection of the vacuum breakers with the dryvell slightly i pressurized indicated that most of this leakage was through five of the - l
- vacuum breakers. This inspecti;n also confirmed that any chaft leakage {
as a result of removing the packing is insignificant with respect _to total !
! leakage. Also noted was the inability to accurately determine the va3ve ;
l position from the presently installed position indication system. {
- The torus-to-dryvell vacuum breaker position is detected by limit switches j that are actuated by small arras attached to the valve shaft. The disc i 3
, must travel a considerable distance before sufficient shaft rotation has I
! occurred to actuate the limit switches. Adjusting the limit switches to detect small. openings of the vacuum breaker is difficult. ;
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.k-As a result of these findings, a program was undertaken by the licensee, !
with assistance from the architect-engineer and the reactor vendor. . he l' objective of this program was to develop appropriate modifications for l
installation during the refueling outage scheduled to commence March 2, '
1973 An augmented surveillance test prog mm was developed and conducted 7 for the intervening period of continued c.peration.
i Valve operability was tested monthly by remote cycling with the air opera- l Since the present limit switch armngement cannot detect small open-tors.
ing of the valves, the operability test was followed by a leak test measure-ment. .
The drywell pressure is increased to about 0.25 to 0 50 psid with respect I to the vetvell. The nitrogen supply is isolated and the subsequent dryvell i to vetvell pressure transient is monitored. he 2 psig high dryvell pres- l sure set point is not exceeded. The 0.25 to 0 50 psid test pressure pro- (
vides adequate margin against a spurious isolation.
l The smallest pipes whose failure could result in a dryvell-to-vetvell leak- l age path are the one-inch vent drain lines.' The sensitivity of the interim ,
leakage test is such that it would detect the rupture of one of these drain I' lines. This is accomplished by comparing the differential pressure decay rate to the equivalent differential pressure decay rate calculated for a )
one-inch orifice.
Analyses show that with an initial differential pressure between the. dry- !
well and vetvell of 0.25 to 0 50 psid, the differential pressure vill decay to about 1/2 the initial value in 15 to 25 minutes through a 1" orifice.
Therefore, a criteria that the differential pressure between the dryvell andvetvellmustbegreaterthan1/2theinitialvalueattheendofa l one-half hour period demonstrates that a bypass area of less than a one-inch orifice exists. Results of this interim surveillance program have demonstrated a tendency of_ increased leakage although all tests were'within acceptable limits.
III. Vacuum Breaker M3difications I .
Bree modifications are planned to be made to the vacuum breaker system during the current refueling outage.
A. Improvement of Valve Closing Stroke to Provide Further Assurance of Proper Seating he counter weight arms on the vacuum breakers vill be adjusted so they are in the veritical position when the disc is in the seated position, and 10 pound weights vill be located on each arm 91/4" from the pivot
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2 points. Bis modification vill provide a more constant closirg moment over valve travel and further assure proper seating.
The maximum closing moment that can be attained with the existing con-figuration is shown in Figure 2. With the counter-balancing ams 300 fmm the vertical as they were prior to the modification in the seated position, only 95 5 inch-pounds of closing moment is realized. me frictional resistance in the stuffing box and shaft assembly is of this !
order of magnitude as evidenced by the tendency for the valve to stick l slightly open; hence it is necessary to increase the closing moment l j
vhen the valve is at its seat to ensure sufficient closing moment is !
present to overcome friction. To accomplish this, the counter-balanc- j ing ams are rotated to the vertical position when the valve is closed.
This eliminates the effect of the counter-balance when the valve is l seated but allows counter-balancing of the disc assembly as the valve l is opened. The addition of weights to the counter-balance ams pro- l vides a means of adjusting the maximum closing moment with the valve .
open. As shown in Figure 2, with the arms in the vertical position and with 10 pound weights placed 91/4" from the pivot points, 242 inch- l pounds of closing torque is realized in the seated position. Having j the ams in the vertical vith the valves seated nullifies the effect of the weights in this position, however, when the valve is full open the closing moment vill be lowered to the indicated value of 362 inch-pounds. With the addition of frictional resistance, a combined moment !
of 338 inch-pounds must be overcome to lift the valve off its seat.
The valve disc has 254 square inches of ama exposed to the differential 1
pressure and this area has an effective moment am of 113/8" to the
- valve pivot. Consequently the valve vill begin to open at .1165 psid.
B. Replacement of Snap Lock Limit Switches with Micro Switches to Improve Position Indication i
The valve-closed position indicator switches will be replaced with Honeywell Model #21S111, heavy duty, micro switches capable of de-tecting any non-closed vacuum breaker at a degree of opening less I than that pemitted for a single valve.
Tbe maximum allovable bypass area is equivalent to a six-inch line which translates into a disc opening for all ten valves of 0.04" at all points around the circumference of the valve disc, or 0.08" open at the bottom of the disc when the top of the disc is on its seat. For a single vac-uum breaker, the =vi== anovable bypass area is 0 375" at an points around the circumference or O.75" at the bottom of the disc with the top d
l l s 1 of the disc at the seat. This latter linear displacement of the disc is approximately equivalent to a 20 angular displacement of the valve l shaft. Le replacement switches are rated for the following: )
! 1. Standard in-line actuation !
- 2. Iov (36 oz) operating force plunger seal ,
3 Sealed head and contact block cavity protects internal parts l from oil, coolants, water, dust and chips j 4. Two circuit double break, rated for 10 a=ps,120, 340 or 480 V ac l
l 5 Pretravel to operating position .065" maximum, over-travel O.219" l
minimum, differential travel to 2elease position .009" minimum i
It is not expected that the full potential accuracy can be re-lized due to variations introduced in the actual muc. ting of the svtiches in the valve body. However, it is expected that the micro switches mounted l at the bottom of disc vill be sufficiently accurate to detect movement l
ofthediscwithin1/8"offthebottomoftheseatingarea. In summary, ;
the planned installation of two limit switches in the vacuum breaker i body has been reviewed in regard to:
- 1. Redundancy of operation l l
- 2. Meeting IEE-279 standards l 3 Physical installation on valve Redundancy is provided by installing two limit switches to detect tie j closed position. Existing limit switches vill continue to monitor the i open position. Since the purpose of these limit switches is to pmvide j l
information to the cperator, physical separation of the control viring l l or indicating lights is not required. Existing viring vill be utilized i with the new limit switches connected in place of the existing limit switches. This connection vill provide redundant signals to the control 1 l room.
C. Upgrading of Corrosion Resistance of the Air Operators to Further Ensure Testability he internals of the air operating assemb3v for the 18" torus-to-dryvell vacuum breaker are to be electroplated for corrosion resistance. The piston cylinder, spring spacer, pistion, and upper cylinder cap are to be plated with 1 mil thickness of nickel. The spring is to be cadmium coated.
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! t l Technical Specification 4.7.A.4 requires that eight of the ten dryvell- !
j pressure suppression chamber breakers shall be openble at all times
! when the primary containment is required. he testable feature of the
- vacuum breakers allows verification of ope nbility. Experience bes :
shown that the air test operators am subject to corrosion. Corrosion ,
, accumulation may pnvent testing of a particular vacuum breaker or ;
interfere with return of the vacuum breaker to the fully seated posi-
, tion. Application of corrosion resistant plating to the exercise ;
- . cylinder internals will ensure proper operation of the exercise feature
! and provide additional assurance of vacuum breaker operability. l D. Surveillance Following the Modifications
- 1. Preoperational Tests .
1 Prior to resuming power operation after the. refueling outage the ,
1 vacuum breakers vill be preoperationally tested to verify the
' modifications. Thesc tests vill include a stroke test with the air operators and verification of indicating system. In addition, switch reset will be verified by manually pushing the disc off its seat with a deptb gage and recording the lineal distance at which the indicating light is extinguished. All switches should reset
! within1/8"ofdiscmovement. he closing moment will be measured by applying a torque vrench to the valve shaft and recording the torque required to just lift the dire off its seat and the torque required to hold the disc fully open. If required, adjustments f vill be made so that the torque at full open does not exceed 362 4 inch-pounds.
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- 2. Exercise Testing
] Following completion of the proposed modification and the verifi-i cation of position switch accuracy, the nomal surveillance program
- vill be resumed and vill be basically as described below.
! Once each month during operation all vacuum breakers win be individ-ually cycled to verify proper operation. Should any valve fail to indicate closed-following cycling, a pressure test will be performed.
Bis tect vill be essentially the same as the interim leak test de-1 scribed earlier.
1 3 Routine leak Test In addition, the following routine leak test is proposed. Se ob-jective of this test win be to detect flow paths between the dry-
- well and vetvell whose total capacity is. equal to or greater than the capacity of a one-inch diameter plate orifice. A combined leakage capacity less than this vill be considered acceptable.
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? Using the dryvell vent / purge system, the dryvell pressure vill be increased by at least 1 psi with respect to the vetvell pressure
! and held constant. The 2 psig isolation set point win not be
} exceeded. he subsequent vetven pressure transient (if any) vill I be monitored with a sensitive pressure gauge. If the dryvell pres-j sure cannot be incraased by 1 psi over the vetvell pressure, it i l would be because a significant leakage path exists; in this event,
) the lea'. cage source vin be identified and eliminated before power operation is resumed. _j
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! Figure. 3 shows the dryvell and vetvell pressure transients assuming i a :;ne-1neh orifice leakage path and assuming the dryvell pressure
! vas increased to 1.25 psi in a 5-minute period.. Figure 4 shews the j mssure diffenntial between the dryvell and vetvell.
3 associated Bem iE a1 p/4 hour period during which the differential would be.
! greater than 1 psi, thus there would be ample time to conduct a l 3 0-state test.
3 l 'Ene dryvell to vetvell leak test will be perfonned at the end of j each operating cycle and before power operation is resumed; during this time, there vill be no energy dumps to the pool and a constant
,j temperature condition is expected to exist in the suppression cham-i ber at the time of the test.
1 I During the test period there shall be no operation of the following j equipment:
l l a. Be RER System in either the containment spray or pool cooling 4 mode
- b. LPCIS l a 1
- c. HPCIS i
I d. Iblief valves i l The test will be conf.ucted prior to pressurizing the primary system'-
l i following refueling; under these circumstances there can be no oper '
l ation of the LPCIS, HPCIS or relief valves. Should the reactor be
- pressurized at the time of the test, prohibiting thc operation of l any equipment that can dump energy to the pool un enhance temper-l atum stability.
i i IV.- Safety Considerations A. Leakage Limits i
The Monticello containment has been examined to determine vbar leakage between the dryvell and vetvell can be tolerated. Figure.5 shows the
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allovable leakage capacity, A/ f, as a function of primary system break s.rea. (A is the area of the leaka6e Path between the dryvell and vetvell, and K is the total geometric loss coefficient associated with A.) For co=parison, Figure 5a translates A/ % into equivalent orifice by assuming a geometric loss coefficient of 2.69 ]
The allowable A/ h is determined on the basis of the allowable sten = '
1 mass that can be passed, the A P between the dryvell and vetvell, and the bypass duration.
The maximum AP between the dryvell and vetvell varies as a function of primary system break size. For large breaks the dP is high, but ,
lasts for a short duration. The maximum d P would be for the DBA, !
and would also be for the shortest duration. Primary system breaks greater than 0 3 fta vill result in rapid depressurization of tne primary system. Figure 6 shows the containment transient associated with breaks in this range. For a given primary system break, the =
allowable leakage capacity would result in the containment pressure ;
being equal to the design pressure at the end of the reactor blowdown i period.
For small primry system breaks the dip between the vetvell and dryvell ,
is equal to the downcomer submergence (1.8 psi), while vent flov losses j are negligible. %ese breaks,11ovever, do not depressurize the EPV rapidly and some operator action is required to terminate extended by-pass duration. %ese small leaks are the most limiting and result in the maximum allowable leakage capacity.
As part of the overall evaluation of the leakage test, the containment response has been analyzed assuming the maximum leakage capaelty allowed by the test to actually exist at the time of a primary system blo down.
Se complete spectrum of primary system break sizes was investigated.
The containment response to large primary system ruptures was found to be es'entially unaffected by the existen :e of a one-inch orifice leak-age path between the vetvell and dryvell. Bis is because during the reactor blowdovn period (up to 10 minutes) essenticlly all the blow-down flow goes through the main vent system and is condensed in the i suppression pool. The coasequences of a giren leakage path incressc.
as the size e the postulated primary system break is reduced; the sorst .t.se erresponds to small steam breaks that continuously inject ttea:a inte i.ne containment but are not sufficiently large to result ir primary system depressurization due to either break flow or ECCS operation.
For ',m se small breaks, intemittent operation of either the LPCI, HPCI or fet:% ster systems maintains an adequate coolant inventory and the core r? y power maintains reactor pressure near rated. Bus, blowdown flow ain leakage flow vill continue until the reactor is depressurized.
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' Figure 7 shows the response of the containment to a small break (0.025 ft2). Be analysis assumed that: (1) reactor pressure re-J mains at rated, (2) a leakage path equivalent to a one-inch orifice exists between the vetvell and drycil and (3) there is no condensa-tion of the steam flowing through the leakage path. In practice most of this flow would either condense on the large peol surface or be condensed by the activation of the dryvell sprays.
Even under these degraded conditions, the containment design pressure l vould not be approached for 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />. B us the plant operators have a=ple time in which to shut the plant down in an orderly manner.
Le current vetvell spray system has sufficient capacity to condense all the steam that could flow through a one-inch orifice leakage path.
If the plant operator activates these sprays shortly after the break has occurrec, there vill be no long-term pressurization of the con-tainment due to leakage flow. - j However, in regard to the containment spray, analysis for the type of break considered here has been made and is included in the FSAR. No credit was taken for the potentially beneficial effects of the spray systems; the progression of events under the postulated conditions is not, and should not, be dependent on spray system operation.
Procedures may, however, be devised to initiate the sprays as a man-
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ual function to mitigate overall effects that in themselves would not result in consequences more severe than those previously ana-lyzed for which adequate non-spray protection exists.
'Ib include sprays in the sequence for protection against the breaks
- hypothesized is to imply their need in other, more severe break situ-
. ations for which analysis indicates they are not necessary.
l It is recognized that any action that would aid in minimizing the effects of breaks is definitely advantageous and should se considered I as an operating option. Such options, however, must be treated as additional conservative elements in the analysis that may be excluded without jeopardizing the safety of the plant or its ability to sustain j the postulated event.
he following table shova a postulated sequence of events between the time the accident occurs and the time the reactor pressure is reduced to O psig, and the transient terminated.
In both cases the pressure is down to O psig in 5 botts; this is well a
within the theoretical limit of 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />.
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1 Normal Auxiliary Power Available_ Plant Operating on Station Diesels l
- 1. Accident occurs. 1. Accident occurs, off site power )
- lost. j
- 2. High dryvell pressure semms 2. High dryvell pressure scrams reactor. Suppression chamber reactor. Suppression chamber reaches 20 psig and continues reaches 20 psig and continues to increase at av 3 psi /hr. to increase ~ 3 psi /hr. l 3 After short period, operator 3 Loss of condenser vacuum pre-decides to cool down and start vents use of main condenser.
to dump to main condenser at a Operator decides to cool down 1 ratethatgivesa1000F/hr by dumping steam to the pool !
cooldown rate, via relief valves at rate that will give a 100 F/hr cooldown.
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- 4. Feedvaterand/orHPCImaintains 4. Adequate coolant inventory is l adequate coolant inventory. maintained by HPCI. ;
l 5 Operator starts vetvell sprays 5 Operator starts vetvell sprays i
, after the accident and thus shortly after the accident and ;
condenses all leakage flow. thus condenses all leakage flow.
Containment pressurization Containment pressurization ,
ceases. ceases.
- 6. At 50 psia in the reactor and 6. At 50 pain in the reactor and following RERS flushing, the following RHRS flushing, the RHRS is put into the shutdown EHRS is put into the shutdown mode. Cooldown continued. mode. One EHRS heat exchanger
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and pu=p is sufficient to con-tinue cooldown.
7 Reactor pressure down to 14.7 Reactor pressure down to 14.7
< psia 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after the accident, psia 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after the accident.
Thus, the existence of a leakage path whose capacity $s slightly less than the aximum permitted by the routine leak test will allow the reactor operator to shut down in a normal manner following a small unisolable steam leak inside the containment.
FortheMonticeglounit,themaximumallovableleakagecapacityisan A/ NIII = 0.12 ft . Typically the geometric loss factor would be 3 or greater, thus the actual allowable leakage area would be 0.2 ft2 ; this corresponds to a 6" line. It should be noted that a one-inch plate ori-ficehasanA/ = 0.0033 ft2. Thus, the leakage test vill detect a leakagepathwh[osecapacityisonly3%ofthemnv4=_mallowable.
When calculating the allowable leakage capacities shown in Figure 5, the following sequence of events is assumed. Immediately after a small primary system break, a rapid rise in containment pressure would occur as the non-condensible gases in the dryvell are washed over to the suppression chamber. During this portion of the transient, a the assumption is made that the plant operators assume everything 18 normal, i.e. , no leakage path exists. Under nomal circumstances the maximum pressure calculated to occur in the suppmssion chambers of the Monticello unit is 30 psig. This is the pressure that would result if all of the non-condensible gases initially in the containment are carried over the the vetvell free space. For the allowable leakage calculations, the plant operators are assumed to be unaware that a
- leakage path exists until the suppression chamber pressure reaches 35 psig. Further, a 10-minute delay is assumed before any action is taken to teminate the transient.
The corrective action taken 10 minutes after the pressure has exceeded 35 psig is assumed to take 5 minutes to be effective. Figure 8 shows the sequence of events for a typical small break. For the calculations, the specific nature of the corrective action taken after 10 minutes was not defined; the operators have several options available to them. If the source of the leakage is undefined, they would probably depressurize the primary system via either the main condenser or relief valves (ADS).
When nalculating the allowable leakage capacities shown (Figum 5) the following assumptions were made. Flow through the postulated leak-
- age path is pure steam. For a given leakage path, postu3 ting that the leakage flow consisted of a mixture of liquid and vapor vould increase j the total leakage mass flow rate but would decrease the steam flow rate.
Since it is the steam entering the suppression chamber free space that l is resulting in the containment pressurization, this is a conservative assumption.
There is no condensing of the Jeakage flow on either the suppression pool surface or the torus and vent system structures. Because conden-sation results in less steam being in the suppression chamber free space, this is a conservative assumption. In practice thert. would be condensation, expecially for the larger primary system breaks, when there would be vigorous agitation of the pool surface during blowdown.
If the source leakage is a malfunctioning vacuum breaker, the operator vould be alerted by the redundant control room vacuum breaker position indicators. In tbis event, the operators would attempt to close the open valve by exercising it with the remote actuator. ' Ibis action, together with tl.e force acting on the valve disc as T result of the flow that is ocenrring, would in all probability close the valve. ,
l l
l B. Flow Considerations Calculations were perfomed, based on the modified balance am con- i figuration, to determine the flow versus area characteristics of the I vacuum breakers. It was detemined that dynamic forces were sufficient that the valve would be held fully open with a mass flow rate to the drywell of approximately 23 lbm/sec. 'lhis corresponds to a differential pressure of approximately 0.8 psid (based on dry nitrogen at standard temperature and pressure. ) Below 0.8 psid, it was determined that the valve bypass area varied with the flow rate. 'Ihis relationship was ex-i amined by assuming that the flow velocity head acted as a counter-balanc-ing force to the closing moment. Since the closing moment increases with the angular displacement of the valve shaft, the flow rate must also de-crease with the angular displacements. 'lhese calculations are summarized
- in Figure 9, which shows the flow rate versus the angular displacement of the valve shaft. The angular displacement is correlated to flow area in Figure 10.
V. Technical Specification Considerations Proposed Technical Specifications will be submitted separately after the necessary reviews are complete. Consideration is being J iven to adding the following conditions and surveillance requirements.
Limiting Conditions for Operation 3 7.A.h Drywell-Pressure Suppression Chamber Vacuum Breakers
- a. When primary containment is required, all drywell-suppression chamber vacuum breakers shall be operable and positioned in the closed posi-tion as indicated by the position indication system, except during testing and except as specified in 3 7. A.4.b and c, below.
- b. Any drywell-suppression chamber vacuum breaker may be non-fully closed as ind!cated by the position indication system provided that a drywell to torus pressure differential can be maintained within allovable limits for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> with no N2 makeup,
- c. Up to two dryvell-suppression chamber vacuum breakers may be deter-mined to be inoperable for opening provided that they are secured in the closed position.
- d. If Specifications 3 7.A.4.a, b or e cannot be met, the situation shall be corrected within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the reactor shall be placed in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
. - - . ~~ . - ._. .- - - . . ..
i j i 1
i l Surveillance Requirements l
h.7.A.h Dryvell-Pressure Suppression Chamber Vacuum Breakers
- a. Each dryvell-suppression chamber vacuum breaker shall be exercised through an opening-closing cycle monthly.
- b. When it is determined that any vacuum breaker valve is not fully closed as indicated by the position indication system at a time when such closure is required, the apparently malfunctioning vacuum breaker valves shall be exercised and pressure tested as specified in 3 7. A.k.b immediately and every 15 days thereafter until the apparently malfunctioning valves have been returned to normal ser-vice.
- c. Once each operating cycle, each vacuum breaker valve shall be visually inspected to ensure proper maintenance and operation.
- d. A leak test of the dryvell to suppression chamber structure shall be conducted during each refueling outage.
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