ML20236C534
| ML20236C534 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 10/23/1987 |
| From: | SYSTEM ENERGY RESOURCES, INC. |
| To: | |
| Shared Package | |
| ML20236C525 | List: |
| References | |
| NUDOCS 8710270235 | |
| Download: ML20236C534 (9) | |
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LAttachment'1I to J
AECM-87/0190 h7 REACTIVITY CONTROL SYSTEMS BASESL
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STANDBY LIQUID CONTROL SYSTEM (Continued).
With redundant' pumps and explosive injection valves and with a highly reliable control rod scram system,- operation of the reactor is permitted to continue for short periods of tikse with the system inoperable or for longer periods of time with one of the redundant components. inoperable.
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Surveillance requirements are established on a frequency that assures a high reliability of the systemi Once the solution is established, boron con-centration will not vary unless more boron or water. is added,. thus'a check on y?
the temperature and volume once each 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> assures that the solution is.
3 available for use.
T Replacement of the explosive charges in'the valves'at regular intervals'
~will assure thattthese valves will not fail because of deterioration of the charges.
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- Attachment 9II to
.AECM-87/0190- [ j e ' Insert Number 1 To Page B'3/4 1-4a. Compliance with'the NRC ATWS Rule 10CFR50.62 has been demonstrated by means of - the equivalent, control capacity. concept using the plant specific minimum parameters. This concept requires that each boiling water reactor must have a ' standby liquid control system with a minimum flow capacity and boron content- ~ equivalent in control' capacity to 86 gpm for 13% weight sodium pentaborate -solution.(natural boron enrichment) used'for the 251-inch diameter reactor vessel studied in NEDE-24222,. Reference 4. The described minimum system parameters (82.4 gpm, 13.6%. weight with natural _ boron enrichment) provides a equivalent control capacity to the'10CFR50.62 requirement. The' techniques of. the' analysis are presented in a' licensing topic'ai report NEDE-31096-P, f Reference 5. 0nly one. subsystem is needed to fulfill. the system ' design basis, and two-subsystems are neededJto fulfill ATWS' rule requirements. A SLC subsystem.- consists of the-storage' tank, one divisional pump, explosive. type valve, and l associated controls, and'other valves, piping, instrumentation,.and controls necessary to prepare and: inject neutron absorbing solution into the-reactor. 4; " Assessment of BWR. Mitigation'of ATWS, Volume II', NEDE-24222, December 1979. 5. L. B. Claasen et. al., " Anticipated Transients Without Scram, -Response to NRC ATWS Rule 10CFR50.62", G. E. Licensing Topical ' Report prepared for the BWR Owners' Group, NEDE-31096-P, December, 1985. J16AECM87100501 - 12 a
^1 Attachment IfI to AECM-87/0190 A. SUBJECT 1. NPE-87/02C Standby Liquid Control System (SLCS) Pump Relief Valve Setpoint Change 2. Affected Technical' Specifications j a. Reactivity Control Systems Standby Liquid Control System j Surveillance. Requirement, 4.1.5.d.2 - page 3/4 1-19 and B 3/4 1-4a. B. DISCUSSION J The following change is proposed: I 1. The SLCS pump relief valve surveillance is revised requiring a demonstration that the relief valve will actuate within 3% of the SLCS design pressure in accordance with the ASME' Code (Section III, 1 Division 1 Subsection NC-7614.2(b), 1974 Ed.) 1 I 2. The Bases Section-3/4.1.5.is revised to reflect the change. C. JUSTIFICATION 1. The current system design pressure is 1400 psig. SERI intends to reanalize the system to allow raising the relief valve setpoint to j approximately 1500 psig in order to provide additional margin j between the peak oscillations and the relief valve setpoint. This margin will provide additional assurance that the relief valve does not open unnecessarily during system testing and operation. 2. Pursuant to Surveillance Requirement 4.1.5.c, the SLCS pumps must ~; be tested quarterly to demonstrate the capability of developing a minimum flow of 41.2.gpm at'a pressure of greater than or equal to i 1220 psig. The SLCS pumps are piston type positive displacement pumps. Each time the piston strokes the discharge pressure oscillates. At the Technical Specification minimum flow discharge pressure of 1220 psig, each piston stroke causes the discharge pressure to rise approximately 100 psig, bringing the total discharge pressure to about 1320 psig. Technical Specification 4.1.5.d.2 currently requires the pump relief valve setpoint to be within +3% of the nominal valve setpoint of 1400 psig. 3. The relief valves are ASME Class 2 valves and, as such, have a +3% tolerance in the set pressure, per the AFME Code (Section III -- Division 1 Subsection NC-7614.2(b), 1974 Ed.). This piping is ASME Class 2 piping. ASME Section III permits over protection relief valves to be set at the design pressure and requires the relief valve tolerance to be less than or equal to 3%. Therefore, the surveillance requirements of Technical Specification 4.1.5.d.2 will be changed to verify that the relief valve actuates within +3% of the piping design pressure. J16TS87061901 - 1
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- Attachment'III'to f
,AECM-87/0190 y SIGNIFICANT: HAZARDS CONSIDERATION D
- 1.
The proposed changefdoes not involve a significant' increase in the ~ . probability.or consequences'.of an accident previously evaluated. The proposed increase in the pumpLrelief. valve setpoint is within' d ASME Code;allowables ana.will notl increase)the probability of; piping
- failure..'The consequences of previously evaluated' accidents / remain-
. unchanged since the relief valve wi11'still perform.its intended-function of preventingLthe SLCS discharge piping from exceeding its s .' design pressure.:. BasedLupon.-the above,,the consequences of an: accident will;not;be.significantly increased., J2.
- The proposed' amendment does not create the possibility of a new or;,
~ different kind of a'cident.from any:previously analyzed. The safety, c ifunction. performed by the SLCS or the. operability of the.SLCS is not-' , :1affected by the proposed. Technical: Specification revision. The-proposed change will ensure t_ hat the SLCS'will-be able.to. deliver. -i 'its rated'flowrate~to the reactor.'without.the possibility of some
- flow!being div'erted through the relief valve. Therefore, there is; nof possibil,ity of a..new or different kind of.. accident from?any-
previously' analyzed. Hi1
- 3. -
The proposed change'does not involve'a~ significant reduction inia-margin of; safety..The change in the. method of. determining the SLCS zpump relief. valve setpoint is in accordance wit t e ASME Code. As h h such,.the pr.oposed: change does not lead-to a significant reduction in La marginiof safety. s' 1 i ~ I l J16TS87061901 - 2.
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nee -s,/oze. ch REACTIVITY CONTROL' SYSTEMS ,,8 / 9 SURVEILLANCE REQUIREMENTS (Continued) b. At least once per 31 days by; 1. ' Starting both pumps and recirculating demineralized water to the test tank. 2. Verifying the continuity of the explosive charge. l 3. Determining that the available weight of sodium pentaborate is tY greater than or equal to 1bs and the concentration of boron c;5 in solution is within th limits of Figure 3.1.5-1 by chemical ht analysis.* 3F08 0 4. Verifying that each valve, manual, power operated or automatic, in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position ~. c. Demonstrating that, when tested pursuant'to Specification 4.0.5, j the minimum flow requirement of 41.2 gpm at a pressure of greater ,p than or equal to defe psig is met, without actuation of the pump p e-j kl relief valve. WO d. At least once per 18 months during shutdown by; .d .l 1. Initiating one of the standby liquid control system A 4 subsystems, including.an explosive. valve, and verifying that a flow path from the pumps to the reactor pressure vessel is available by pumping. demineralized water into the reactor vessel. The replacement cha'rge for the explosive valve shall be from the same manufactured batch as the one fired or from another batch which has been certified by having one of that batch successfully fired. Both system subsystems shall be tested in 36 months. 2 2. Demonstrating that the pump relief valve opens within 3% of th c:r'n:' ; h: ::t;; int ;f M00 p:ig and verifying that 6)fs b % d*5 Y t e relief valve does not actuate during recirculation to the .j p re.uo re., test tank. 3.
- Demonstrating that all heat traced piping between the storage tank and the reactor vessel is unblocked by pumping from the storage tank to the test tank and then draining and flushing the piping with demineralized water.-
4. Demonstrating that the storage tank heater is OPERABLE by verifying the expected temperature rise for the sodium pentaborate solution in the storage tank af ter the heater is energized. I
- This test shall also be performed anytime water or boron is added to the I
solution or when the solution temperature drops below the limit of Figure 3.1.5-1.
- This test shall also be performed whenever both heat tracing circuits have been found to be inoperable and may be performed by any series of sequcntial, overlapping or total flow path steps such that the entire flow path is included.
GRAND GULF-UNIT 1 3/4 1-19 Amendment No. l
' Attachment III to ( AECM-87/0190 i [ h REACTIVITY CONTROL SYSTEMS BASES STANDBY LIQUID CONTROL SYSTEM (Continued) With redundant pumps and explosive injection valves and with a highly reliable control rod scram system, operation of the reactor is permitted to continue for short periods of time with the system inopetable or for longer ~ periods of time with one of the redundant componer*.. inoperable. Surveillance requirements are established on a frequency that assures.a high reliability of the system. Once the solution is established, boron con-centration will not vary unless more boron or water is added, thus a check on the temperature and volume once each 24 hours assures that the solution is available for use. Replacement of the explosive charges in the valves at regular intervals will assure that these valves will not fail because of deterioration of the charges. Ensarr tivn hay g O Sf0n S d-To ArpJf.Si 'd ( l /?eik[ v o. lv.es provi)td tQ SL C S y my> et on d,%Lme y;y.% 9 to yo tx er t% SLCS pum and pipo%9 honm o&a ry vs.ss u v-e con), b%ns. Tasn { y o f rh reiM va Iv.e sa.r,,et t-e) ve riOy Ey fG+ r% ya ll< f ve j,,x_. a)oa, not f ope n du r ^ 9 l sko y s tute. opa.mtio o} g, f n SL C S p u mp demons % % d)DEtt A SILE T') 6 f he. v.e In't 5 va lv 2., Th e alid volses n( i v2 h 5/h 2 Clnss 2. sis Ive r a.n d, a s s ue.L, kava-a -2 J yo ts-l.enan a In 4 ope n,'ng y w a arx fypm su p rz ss ur-L, far Y bW5 [# # {$s c.Tlo n llI~ - b ivl$je s j fu),jecIlon AI C ~)d/ 4. 2 (0.i 'i GRAND GULF-UNIT 1 B 3/4 1-4a AmendmentHo.2El
i \\ Attachment III to AECM-87/0190 1 Insert Number 1 To Page B 3/4 1-4a 'D Compliance with thc NRC ATWS' Rule 10CFR50.62 has.been demonstrated by means of ) e-the equivalent cont.rol capacity concept using the plant specific minimum o} parameters.. This concept requires that each boiling water reactor must have a kf standby liquid control system with a minimum flow capacity and baron content equivalent in control capacity to 86 gpm for 13% weight sodium pentaborate solution.(natural boron enrichment) used for the 251-inch diameter reactor y i' vessel studiud in NEDE-24222, Reference 4..The described minimum system parameters.(82.4 gpm, 13.6% weight with natural boron enrichment) provides a 4 >- equivalent control capacity to.the 10CFR50.62 requirement. The techniques of N the analysis are presented in a licensing topical report NEDE-31096-P, .( Reference 5. Only one ' subsystem is needed to fulfill the system design _ basis, and two l subsystems'are needed to fulfill ATWS rule requirements. A SLC subsystem consists of the storage tank, one divisional pump, explosive type valve, and associated controls, and other valves, piping, instrumentation, and controls necessary to prepare and inject neutron absorbing solution into the reactor. N 4. " Assessment of BWR Mitigation of ATWS, Volume II', NEDE-24222, g e-December 1979. uj 5. L. 8. Claasen et. al., " Anticipated Transients Without Scram, d Response to NRC ATWS Rule 10CFR50.62", G. 2. Licensing Topicel Y Report prepared for the BWR Owners' Group, NEDE-31096-P, December, C"' 1985. 1 3 T l 1 i .J16AECM87100501 - 12
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e 1 n. L( Attachment VI1to
- AECM-87/0190=
f f BEFORE THE: UNITED-STATES NUCLEAR REGULATORY COMMISSION L LICENSE N0. NPF-29 DOCKET N0. 50-416 IN THE MATTER OF MISSISSIPPI POWER & LIGHT COMPANY-and. SYSTEM ENERGY RESOURCES, INC. and j SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION - 1 AFFIRMATION I, 0. D. Kingsley, Jr., being duly sworn, stated that I am Vice' President, Nuclear Operations of System Energy Resources, Inc.; that on behalf of System Energy Resources, Inc., and South Mississippi Electric Power Association.I am authorized by. System Energy Resources, Inc. to sign and file with the Nuclear Regulatory Commission, this application for amendment of the Operating License of the Grand Gulf Nuclear Station; that I signed.this application as Vice President, Nuclear Operations of System Energy Resources, Inc.; and'that the' statements made and the matters set for rein are true and correct to the best of my knowledge, information and el f. s . \\
- 0. D vKingtl STATE OF MISSISSIPPI COUNTY OF HINDS Public in and for the SUBSCRIBED AND SWORN T0 before,'me, a Notary /)c7%fc, o
, 1987. County and State above named, thiscWJafday of Notary Public My commission expires: Ny commisskm n*s Aug. 5,1993 J16AECM87100501 - 4 _ _ _ _ _ _ _ - _ -}}