ML20053C815
| ML20053C815 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 05/19/1982 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | Bauer E PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| References | |
| NUDOCS 8206020592 | |
| Download: ML20053C815 (33) | |
Text
{{#Wiki_filter:- DISTRIBUTION: ) Docket File bcc: NRC PDR LB#2 File Local PDR EHylton NSIC HAbelson PRC I&E 'O M M.O!50 3 W 353 P ACRS (16) Lewis, OELD e A DZiemann, DHFS M g WLong, DHFS 7; 7 f *'. ' O ; G 9 Mr. Edward G. Bauer, Jr. dl O 7,_ \\ Vice President & General Counsel %y[6g / Philadelphia Electric Company T / A' %g?a.,/Tec Wr 4 2301 Market Street E Philadelphia, Pennsylvania 19101 / 11 //
Dear Hr. Bauer:
4
Subject:
Request for Additional Information - Limerick The Procedures and Test Review Branch has reviewed the initial test program described in Chapter 14 of the FSAR. This review has indicated the nce.1 for the additional information delineated in Enclosure 1. Please note that this information request was prepared prior to receipt of Revision 3 to the FSAR. Please provide us, within 7 working days from receipt of this letter, with the date(s) on which you plan to respond to the above. Any questions concerning this information request should be directed to Dr. Harvey Abelson (301) 492-9774, the Licensing Project Manager. Sincerely, A. Schwencer, C.ief Licensing Branch No. 2 Division of Licensing
Enclosure:
As stated cc: See next page 8206020 W A D..L PM. . D..L.M......./..B..C.... OF FICE ) ..................a.... ... a a a.aa.aa.a* ASdh tunuue >.f.M .t.....V#.n,qs,t,, 5/.17../ 82 5 _ .../..../. 8 2 of.n p nac ronu sia cio noi sacu cao ( OFFIClAL RECORD COPY useo: mi-oss-m
s 6 'ite. Edward Gr .uer,'or. Vice Preside & General Counsel Philadelphia Eler'ric Company 2301 Market Street 19101 Philadel' 1,. Pennsylvania cc: Troy B. Conner, Jr., Esquire Charl'es W Elliott, Esquire ~ Conner & Wetterhahn Thomas & Hair 1747 Pennsylvania Avenue, NW 123 North Fifth Street Washington, D.C. 20006 Allentown, PA 18102 l Mr. Robert W. Adler Judith A..Dorsey, Esquire l Assistant Counsel Limerick Ecology Action Commonwealth of Pennsylvania, DER 1315 Walnut Street, Suite 1632 i 505 Executive House Philadelphia, PA 19107 P.O. Box 2357 i Har Tsburg, PA 17120 Mr Karl Abraham Public Affairs Officer Honorable Lawrence Coughlin Region I i House of Representatives U.S. Nuclear Regulatory Commissir.,n Congress of the United States f 31 Park Avenue Washington, D.C. 20515 King of Prussia,'PA 19806 Roger B. Reynolds, Jr., Esquire Mr. Jac.:que Durr 324 Swede Street Re'sWent~ Inspector Norristown, PA 19401 U.S. Nuclear Regulatory Commission P.O. Box 47 Joseph A. Smyth Sanatoga, PA 19464 Assistant County Solicitor County of Montgomery James M. Neill, Esquire Courthouse Associate Counsel for Del-Aware Morristown, PA 19404 Bcx 511 Dublin, PA 18917 Eugene J. Bradley Philadelphia Electric Company Joseph H. White III Associate General Counsel 11 South Merion Avenue 2301 Market Stree.t Bryn Mawr, PA 19010 Philadelphia, PA 19101 Dr. Judith H. Johnsrud j Mr. Vincent Boyer Co-Director Senior Vice President Environmental. Coalition on Nuclear Operations Nuclear Power Philadel phia Electric Company 433 Orlandt Avenue 2301 Market Street State College, PA 16801 Philadelphia, PA 19101 Thomas Gerusky, Director Mr. Marvin I. Lewis Bureau of Radiation Protection i 6504 Bradford Terrace Dept. of Environmental Resources Philadelphia, PA 19149 Sth Floor, Fulton Bank Bldg. Third & Locust Streets 4 Frank R. Romano, Chairman Harrisburg,.PA 17120 i Air & Water Polluti:n Patrol i 61 Forest Avenue Director, Pennsylvania Emergency i Ambler, PA 19002 Management Agency i Basement, Transportation & Safety Building i Harrisburg, PA 17120 I l I
John Shniper Lawrence Brenner, Esq., Chairman
- Meeting House Law Bldg. & Gallery Administrative Judge i
Mennonite Church Road - U.S. Nuclear Regulatory Commission Schuylkill Road (Rt. 724) Spring City, PA 19475 Was,hington, D.C. 20555 Dr. Richard F. Cole
- i Robert L. Anthony Administrative Judge i
Friends of the Earth of the U.S. Nuclear Regulatory Commission j Delaware Valley Washington, D.C. 20555 i 103 Vernon Lane, Box 186 Moylan, PA 19065 Dr. Peter A. Morris
- Administrative Judge Alan J. Nogee U.S. Nuclear Regulatory Commission
.l The Keystone Alliance Washington, D.C. 20555 3700 Chestnut Street Philadelphia, PA 19104 W. Wil son Goode Managing Director City of -Philadelphia i Philadelphia,~PA 19107 ~ ~~ William A. Lochstet i 119 E. Aaron Drive State College, PA 16801 Walter W. Cohen j Consumer Advocate Office of Atto'rney General 1425 Strawberry Square Harrisburg, PA 17120 i 1 Steven P. Hershey, Esquire j Consumers' Education & Protective Association Sylvania House Juniper & Locust Streets i Philadelphia, PA 19107 Sugarman & Denworth S,ui.te 510 't North American Building j 121 South Broad Street Philadelphia, PA 19107 l f Donald S. Bronstein, Esquire i The National Lawyers Guild j Third Floor 1425 Walnut Street j Philadelphia, PA 19102 4 i
ENCLOSURE 1 L J'f STAFF POSITIONS AND REQUESTS FOR ADDITIONAL INFORMATION .. A
- 5 LIMERICK GENERATING STATION, UNITS 1 &2 y
INITIAL TEST PROGRAM 640.1 Regulatory Guide 1.20, " Comprehensive Vibration a y. (1. 8) Assessment Program for Reactor Internals During ?g ' Preoperational and Initial Startup Testing," Kd Section De indicates that the NRC staff uses fjl this guidance for evaluating submittats,for g (y operating license applications docketed after [. June 22, 1976, or construction permit applications docketed after June 22, 1976. h k Thereforer Regulatory Guide 1.20 is applicable p e. to Limerick. Modify FSAR Section 1.8 accordingly. (( y,'; 640.2 Modify test descriptions for post-accident f! (14.2.12) ESF-related air filtration systems to include if N inplace filter testing. k.. t 640.3 The following exceptions.to Regulatory Guide [ ~ ? (1. 8) 1.68, " Initial Test Progr'ams for Water-cooled h (14.2.7.2) Nuclear Power Plants," (Revision 2, 8/78) as
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b stated in FSAR Subsection 14.2.7.2 are not }! adequately j u s t i f i e d.- (1) Exception (a) to Regulatory Guide 1.68, Section C.1: S e c t i on 14.2.7.1 and accompanying references do not k C; adequately establish the alternative y criteria for the selection of systems
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- t 4
requiring t'esting. Delete this exception or provide technical Il justification for not testing any j system which meets the followin,g o 3] criteria: l Ca) Will be relied upon for safe shutdown and cooldown of the [! 'l reactor under normal plant conditions and for maintaining j f the reactor in a safe condition i for an extended shutdown period. I (b) Will be relied upon for safe tl shutdown and cooldown of the r reactor under t ransient (infrequently I i or moderately fr'equen't events) conditions and postulated accident conditions and for maintaining the li reactor in a safe condition for an N i extended sh'utdown period following q such conditions. i (c) Will be relied upon for establishing ii conformance with safety limits or q .I limiting conditions for operation 'l that will be included in the I facility technical' specifications. j (d) Are classified as engineered safety 1 d features or will be relied upon to 4
1
- jft support or assure the oper,ation of engineered safety features within 1
4 design limits. (e) Are assumed te function or,for which credit' is taken in the accident analysis for the facility (as. described in the Final Safety Analysis Report). (f) WiLL be utilized to prccessi store, controle or limit the release of I radioactive materials. to Reguhatory Guide 1.68, - (2) Exception (b) lj Section c.4: Delete this exception and .i l modif y FSAR Subsection 14.2.11 or provide an alternative s c h e d u'l e f o'r submission ~ of preoperat'ional an[d startup test
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procedures which is acceptable to the Region I Administrator. 1 4 ) q 1 3 1 1i 1 t
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.8 i
4_ F.t (3) Exception (c) to Regulatory Guide 1.68, Section C.9: Delete this exception; a Summary Startup Report will be required by. Technical Specifications,,Section 6.9 i for initial and reload startups. ~ i ~ (4) Exception (d) to Regulatory Guide 1.68e l Appendix A: This is not an exception and should be deleted. (5) Exception (e) to Regulatory Guide 1.68, Appendix C Paragraph 1.h: FSAR Section 14.2.9 as presently written does not constitute an e x c 6% t i o n.- thereforer - this exception should be deleted. 640.4 Modify the listing f or -Regulatory Guide 1.68 (14.2.7.2) to reflect the required revisio'n; Revision is l July 1978. 640.5 Add a description of the extent of compliance (14.2.7.2) with testing prescribed by NUREG-0554 " Single-Failure P' roof Cranes for Nuclear Power Plants" and NUREG-0612 " Control of Heavy Loads at Nuclear Power Ptahts" to your statement in 14.2.7.2 regarding r ? Regulatory Guide 1.104. 4 4 } ~ i l il lA
m i 640.6 Modify the regulatory guide listing to (14. 2. 7. 2) reflect the correct revision of Regulatory Gu ide 1.108 (Revision is August 1977). 640.7 Provide the appropriate referencer, in (14.2.7.2) 14.2.7.2, for Regulatory Guide 1.140, "Designe Testing, and Maintenance Criteria for Normal Ventilation Exhaust System Air l Filtration and Adsorption Units of Light-Water-cooled Nuclear Power Plants" Position C.S. 640.8 Certain terminology used in the individual (14.2.12) test description does not clearly indicate - the source of the acceptance criteria to be used in determining test adequacy, an acceptable format for providing' acceptance criteria for test r e su l' t s includes any of the fotLowing: Referencing technical specifications (Chapter 16), Referencing accident analyses (Chapter 15)r Referencing other specific sections of the FSAR (e.g.i 7.4.1.2) or topical reoortsi 4 p 2
4 a mA m 6-Referencing vendor technical manua.ls i and test specificationsi Providing specific quantitative bounds j. (only if the information cannot b,e
- )j provided in any of the above ways).
f Preferably, test descriptions should. I discuss the sources or bases of acceptance criteria in lieu of identifying actual quantitative values. Modify the individual test descriptions ) presented below to provide adequate acceptance criteria ore iftapplicablee paragraph to Subsection 14.2.12 that I add a .J. j provides an acceptable description to each i of the following unclear terms,found in f the identified tables. (1 ) Operablee occurs property, controlled properlys proper, normale operate properlyr f u n c t i~o n properlyr I ,l pe'rform properlye ,l Tab le 14.2-3 SUT-1e SUT-5, SUT'-7e i 1 ' l, SUT-30, SUT-33. i 's i s I T ~, t
... ~. .. ~.. _,_.c .l - i Table 14.2-4 P-2.1, P-4.1 (4 times), P.S.1 "t (twice), P-6.1 (twice), P-13.1 (3 times), P-13.2 (3 times), P-13.3, P-13.4 (twice), P-14.1 (4 times), P-16.1 (6 times), P-17.1, P-18.1 (3 times), P-23.1 (twice), P - 24.1 (4 times), P-25.1 (3 times), P-28.1 (4 times), P.28. 2 (4 times), P-30.1 (5 times), P-30. 2 (t w i ce ), P-31.1 (2 times), P -3 2.1 (6 times), P-34.1 (6 times), P-35.1 (twice), P-43.1, P-44.1 (4 times), P-45.1 (6 times), P-45.2 (3 times), P-49.1 (10 times), P-50.1 (5 times), P-51.1 (4 i times), P-5 2.1 (5 times), P-53.1 (3 times), P-54.1 (3 times), P-55.1 (4 times), P-56.1 (3 1 } times), P-57.1 (twice), P-58.1 ( 3 times), P-59.1, F-59.2 (4 times), P-60.1 (5 times), P-61.1 (4 times), P-64.1,.(6 times), P-68.1 (3 times), P-6,9.1 (4 times), P-70.1 (twice), P-72.1 (twice), P-73.1 (3 times), P-78.1 (5 times), P-78.2 (twice), P-78.3 (3 times), P-t 78.4 (3 times),,P-78.5 (twice), P-78.6 (3 j l 1 times), P-79.1 (6 times), P-80.1 (twice), P-81.1 (4 times), P-83.1 (5 time.s), P-88.1, P- 'I 99.1, P-100.1. ~~ l ( 2) Acceptable, acceptable values, acceptable limits. Yable 14.2-3 S UT-19. (.t w i c e ), SUT-20, SUT-26, i SUT-28, SUT-32 (twice), SUT-36. s
... u.. ~_,_..a Table 14.2-4 P - 2.1, P-4.1, P-5.1, P-6.1, P-13'.1 (twice), P-13.3, P-14.1, P-16.1, P-17.1, 3 P-23.1, P - 25.1, P-30.2, P-35.1, P-43.1 (twice), P-44.1 (twice), P-49.1, P-51.1, P-5 2.1 (twice-), P-53.1, P-54.1, P-55.1, P-57.1 (twice), P-59.3, P-61.1, P-6 2.1, P-64.1,f-70.1, P-73.1, i 1 I P-88.1, P-99.1, P-100.1. (3) Within acceptable values, within acceptable time, within acceptable tolerance, within
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acceptable limits, within acceptable margin,. s within the specified acceptable range, within the limits, within design limits, within speci-l l i fied limits, within applicable limits, within wit'in applicable guidelines, design values, n a' within the operating rangt. Table 14.2-3 SUT-1, SUT-5 (twice), SUT-14, SUT-15, SUT-16, SUT-18, S U T - 21, SUT-22, SUT-27 (twice), SUT-33. T ab le 14. 2-4 P-24.1, P-58.1 (twice), P-59.1 4 (twice), P-79.1, P-83.1. (4) Rated, rated conditions, rated actuations time, nominal rated reactor pressure, designed range, design capacity, design reactor pressure, operating conditions. Table 14.2-3 SUT-6, SUT-12 (twice), SUT-13 (twice), SUT-22 (twice) SUT-27, SUT-30 (twice). l Table 14.2-4 P - 24.1 (twice). e
u i 1 3 1 3 (5) Required, design requirements, conform with I plant requirement, design intent, applicable design criteria. 1 ' l, Table 14.2-3 SUT-1, SUT-6,,SUT-8, SUT-28. 't 'l Table 14.2-4 P-56.1. 4 (6) Satisfactory, satisfactorilp compl.eted, O satisfactory completion, satisfies the require-8 ments of applicable criteria and' calculations, Table 14.2-3 SUT-4, SUT-9, SUT-11, SUT-29, 4 = l SUT-31. 1 Table 14.2-4 P-100.1. 1 1 (7) Specified time, satisfies specified limits, 't j specified flow, specified values, limits I specified in the technical specifications. ( Table 14.2-3 S UT-12, S UT-13, S UT-17, SUT-1 4 21, S UT-3 3. I Table 14.,2-3 P-24.1. (8) S u f f i c'i e n t, sufficiently. l l Table 14.2-3 SUT-4, SUT-6, SUT-7. Table 14.2-4 P-18.], P-69.1. L l (9) Verify, verifies, verified. !l Table 14.2-3 S UT -1, SUT-27.. Table 14.2-4 P-14.1. 1' (10) Adequate. j 1 1 Table 14.2-3 SUT-28 (tQice), SUT-34. ~! I (11) Accordance with the procedures, established i 4 procedures. 4 3 .1 -i
n. -t a 4,' Table 14.2-3 SUT-3, SUT-9. r s (12) Accurate. .y Table 14.2-3 SUT-7.
- l (13)
Correct. Table 14.2-3 SUT-30. i l* (14) Normal. j P - 2.1. Table 14.2-4 l calculated core thermal power, not'significantly (15) greater than pre-analysis, means---reliable analysis. Table 14.2-3 SUT-1, SUT-10, SUT-25. 'I (16) Process variable. l I. Table 14.2-3 SUT-18,.SUT-19. (17) Unexplainably worse. t Table 14.2-3 SUT-20. t, 'i (18) Listed modes, modes of,,, operation. i a! 1 Table 14.2-3 SUT-31. I ] Table 14.2-4 P-16.1. i ~ (19) Capable. i 4 Table 14.2-3 SUT-32. (20) Possibility of damage is minimal. Table 14.2-3 SUT-35. 3 -s l (21) Various. J -~ Table 14.2-4 P-54.1. 1, i.] l
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. __ : _. ~ m um _ i, 3 i 640.9 Several of the acceptance criteria do not ceflect (14.2.12) complete accomplishment of the test objectives. i ..l Modification should be made so that when the acceptance criteria has been met, the test objec- !j tive will have been achieved. Modify the individual test descriptions indicated below to'previde consistency between the test. objectives and the acceptance criteria. t 1 i (1) Table 14.2-3 SUT-7 Test objective is to demonstrate operation of' water level instru- ] mentation under various conditions. Acceptance criteria references,nly, normal operating con-1 's ditions. t (2) Table 14.2.3 SUT-16 Provide acceptance l l criteria for determination of core power dis-1 tribution and for determin,ation of core power 1 4 l symmetry. i (3) Table 14.2-3 SUT-17 Provide acceptance ,{ criteria for evaluation of principal thermal and hydraulic parameters. j (4). Table 14.2-3 SUT-20 Acceptance criteria is very broad a'nd open to interpretation. Does i not ensure that test objectives have been met. 1 1 Acceptance criteria needs to be more specific. i (5) Table 14.2-3 SUT-23 Th'e acceptance criteria .i. I could be met with the reactor shut down. The 1 4 4 1 i
.._,.u.- ,b 'I y j f. acceptance criteria does not ensure that the objectives have been met. (6) Table-14.2-3 SUT-26 Acceptance criteria does not address response to change in recirculating flow and the loading capability in, j master manual flow control mode. 640.10 Review of the preoperational and startup s (14.2.12) test phase descriptions disclosed that the a operability of several of the systems and I components listed in Regulatory Guide 1.68 (Revision 2), AppendihAimaynot be demonstrated. Expand your test descriptions to address the followjng items if applicable j to your facility. (Where information regarding preoperational or startup testing is presented in another section of the FSAR, a cross-reference to that section may be provided in Chapter 14 in lieu of repeating f, j that information.) li (1 ) Preoperational Testing 1 1 1.a(2)(d) Relief valves 1
- 1. a (2) ( i)
Safety valves ~- 1.a(4) Hydrostatic tests i 1.d(3) RHR-relief valves s 1 -I ~ i ~ ~
,y 13 - 1.d(4) RHR safety valves 1.e(5) Steam extraction system 1.e(6) Turbine stope c o n t r o l.i i bypass and intercept h valves I
- 1. e (10)
Feedwater heater and drain 1 systems i j
- 1. f (1 )
Circulating water systems i
- 1. f (2)
Cooling towers and associated i auxiliaries 1.g(2) Emergency lighting 1.h ESF flood protection devices
- 1. h (1 ) ( a)
ECCS expansion and restraint tests
- 1. h (1 ) ( b)
ECCS operability using normal and emergency power supplies
- 1. h (1 ) ( d )
ECCS overpressure protection interlocks t i 1.h(5) cold water interlocks 1.h(9) Containment recirculation fans-- Verify that fan motor current is i within its design value at con-4 ditions representative of accident li conditions. Address such issues { as air density, temperature, humidity, fan speed, anc blade angle. ~ v,
2 14 _ 1 Y ~ 1.i(8) Secondary containment isolation ']* initiation logic tests I 4 3 1.i(9) Containment purge systems 1 1>. 1.i(10) Vacuum-breaker tests 1.i(11) Containment Leak collection and i exhaust systems a ) 1.i(12) Containment air purification and 1 cleanup systems .1 1.i(13) Containment inerting systems 'l I -{ i 1.i(15) Containment penetration pressuri-a zation systems 1.i(17) Secondary containment ventilation a 1 systems ~3 1 1.i(18) Containment annulus ventilation a and cleanup systems 1' 1 1.i(21)- Containment penetration cooling J l systems it . Loose parts monitering system 1.j(6)
- 1. j (10)
Seismic instrumentation a
- 1. j (12 ) '
Failed fuel detection system or J lj fu,nctional equivalent
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-i l, I. 1.j(14) Instrumentation and controls 3 that effect transfers of water 1 r a supplies. t 1
- 1. j (15 )
Automatic dispatcher control 1 a t systems $l1 1,i
15 - t
- 1. j (16)
Hotwe(L level control system
- 1. j (17)
Feedwater heater temperature, Level, and bypass control systems
- 1. j (18)
Auxiliary startup instrument tests
- 1. j (19)
Remote shutdown instrumentation and O controls 1.j(20) Flood detection systems 1.j(21) Reactor mode switch
- 1. j (2 2 )
Containment pressure indication; humidity monitors i 1.j(24) Annunciators ~ Personnel monitors 1.k(2) ~ Lab equipment ~ 1.k(3) for condenser 1.L(5) Isolation.fe,atures offgas 1.L(8) Plant' sampling systems ion Antisiphon devices, high radiat 1.m(1) alarms, and low water Level alarms associated with the spent fuel pool. 1.m(3) Operability and leak tests of fuel pool and refueling canal sectional-izing devices. 1.m(4) D y n a m i.c. t e s t,s (100% rated load) and static tests (100% rated toad) of refueling equipment. 1 ~
,i t -f Fuel pool building ventilation 1.m(6) systems 1.n(6) Reactor coolant sampling systems 1.n(9) Vent and drain sy, stems for poten-tially contaminated areas I i
- 1. n (13)
Communication systems
- 1. n (14 ) ( e )
Radwaste enclosure H&V system; Turbine enclosure H&V system 1.n(15) Shield cooling systems 1.n(18) Heat tracing' and freeze protection i
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1.c(2) Reactor component handling system pr'otective interlocks 1.o(3) Reactor component handling system l safety devices (2) Initial Fuel Loading and Precritical Tests 2.c Final functional testing of the l h reactor protection system. Q 2.d Final reactor coolant system leak j ? rate test. t (4) Low Power Testing Steam-driven engineered safety 4.k features I
4 1 1 .f - 3 (5) Power-Ascension Tests 5.v Main steam and f eedwater systecis 5.w Shielding and penetration cooling systems. On those p,enetrations where coolers are not used, provide a startup test description that will demonstrate that concrete temperatures surrounding hat pene-trations do not exceed design limits. I 5.x Auxiliary systems required to 1 I support the* operation of engineered 3 l safety features. 1 i 5.f.f -Ventilation systems. -~ dynamic response to load 1 5.h.h Plant 'i swings. s 5.k.k Plant dynamic response to loss 2, h of feedwater heater. 1 3 3 1 5 ~ 4 i O m ee I 4 _j
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1 a e I
.m 1 - 1 ) 'l l. ,jt 3 640.11 Revise your FSAR to describe additional testing and training discussed in your ~ 2 Letter of March 6, 1981 to Robert L. Tedesco (NRR), in response to N,UREG-0737 I Item I. G.1.~ You should also provide a I conditional, commitment to the [1 1, Simulated-Loss-of-All-A/C-Test requested h in our letter to Mr. Bauer of 3} January 14, 1981. )l 1 640.12 Describe testing to be conducted in 4 j} conf ormance with Regulatory Guide 1.41, (14.2.12) "Preoperational Testihg of Redundant .1 On-Site Electric Power Systems to Verify Proper Load Group Assignments." This testing must incorporate the following: (1) Provide assurance that a5.l sources of f 1 power supply to vital buses are i, 'l capable of carrying full accident i! i 1 loads. If'some portions of the i. I power supplies cannot be full-load testede provide justification. ] l (2) Verify achievement of stable operation during each test. 1 i I 4 P
h.., ' t ...n s 1 '~ i
- $9.
t 7 ~s. s (3) Verify'that testing is conducted x
- t w i tiboripy on e. po we r source at a time.
e s (4) Verify that buses and equipment :in t load groups not under test are l ,[ s i
- mon [tored to verify absence of l
? , volt' age. See Appendix A of BWR Owners' Group letter J \\ dat ed Fe b rua ry 4,1981 from D. B. Waters to 4 s D. E. Eisennut. J 640.13 F o r 'iC P ot[e r S y s t e d ' t e s t) C P-2.1, P-88.1 ), t plans'to 'er.ify that individual v i (14.2.12) state yot,r 3 cell l i m i,t s a r, e n o t ce'e, c e e d e d du r i n g the. design' discharge test and to demonstrate that the DC'l'oads wis t function as necessary '.,.,to'arsure plant - s a f e t 'y 'at'a battery"termina'l 3 4 f, voltage eq'ual to the acceptance criterion that-bas been established for ninimum battery terminal voltage for the discharge s load test. Assure that each battery charger is cap'able of floating the batter,y on the / bus or recharging the completely discharged battery within 24 hours while supplying the .laraest combined demands of the various \\ s eedy-state ctoads under all plant op,erating conditions. g i .k + q I d' e,k a
+ h. 'r } 640.14 Expand the Instrument Gas System Test (14.2.12) (P-18.1) to address Regulatory Guide '1 1.80, "Preoperational Testing of ] Instrument Air Systems," Regula, tory i I P o s i t i on s C.1 -11 for all station air systems. I 640.15 Expand the Standby Diesel Test (P-24.1) i ] (14.2.12) to include the items listed below. (Alsor .) clarify whether this test is also the same b used to comply with Regulatory Guide test j II H
- 1. 41 ).
s' (1) Demonstration of the full load-carrying la capability for not less than 24 hours; } 22 of which should be at the continuous load rating equiva{ent and two hours at the 2-hour load equivalent (refer to \\ Regulatory Guide 1.108e " Periodic Testing of Diesel Generator Units Used i as Onsite Electric Power Systems at 3 } Nuclear Power Plants (Revision is 5 August 1977), Regulatory P'sition o c.2.a.(3)). i i i d. 1 3J
- a.. =
e. - 21 1 ~ (2) Demonstrate proper diesel operation during load sheddinge verifying i voltage levels and overspeed limits (refer to Regulatory Guid3 1.108 4 Regulatory Position C.2.a.(4)). -l functional capability (3) Demonstrate at full load temperature conditions 4 (refer to Regulatory Guide 1.108 Regulatory Position C.2.a.(5)). (4) Demonstrate the ability to: i load a) Synchronize and transfer between the diesel generator unit and offsite power. b) Isolate and: restore the diesel 2 to i ~ standby status. t (Refer to Regulatory Guide 1.108 Regulatory Position C.2.a.(6)). j Provide test descriptions 1) that will verify 640.16 that the plant's ventilation systems are (14.2.12) within adequate to maintain all ESF equipment i Il range during normal its design temperature l'! operations; and 2) that wiLL verify-that the f 1 emergency ventilation systems are capable J' of maintaining all ESF equipment with,in its '1 ra'nge With the equipment design temperature operating in a manner that will produce the 'k d b ~
.j i d'* 22 - it ' t, i maximum heat load in the compartment. If it is not practical to produce 5 maximum heat loads in a compartmente describe the methods that will_be use.d to verify design heat removal capability I of the emergency ventilation systems. l Note that it is not apparent that post-accident design heat loads wiLL be I produced in ESF equipment rooms during the power ascension test phase; thereforee simply assuring that area temperatures ~ l remain within design L-imi t s du r ing t hi s period will probably not demonstrate the 'e design heat removal.c5pability of these systems. It will be necessary to include measurement of air and cooling water temperatures and flows and the extrapolations j l used to verify that the ventilation systems s remove the p'ostulated post-accident can !}'1 heat loads. n 640.17 Expand the Residual Heat Remova'l (P-49.1) (14.2.12) test objective to include _verificatied that paths for the air-flow test of 3 r< Containment spray nozzles overlap the e i q 4
a, :._ i i 4 ..r i. j water-flow test paths of the pumps to 1 demonstrate that there is no, blockage 7 in the flow path. 640.18 Our review of licensee event reports has (14.2.12) disclosed several instances of RCIC pump i failure to start on demand. It ap' pears j:s that many of these failures could have i been avoided if more thorough testing had been conducted during the plant's } 1 initial test programs. In order to discover any problemq affecting pump ti ~ ~. startup and to demonstrate the -j 3 reliability of your RCIC systemi state a your plans to demonstrate coldi quick j pump starts during your initial test i program. 1 J 640.19 Verify that sources of water and associated (14.2.12) pumps used for long-term post-accident i i 1 core cooling will have adequate NPSH and s absence of vortexing over range of l the } 1 basin level from maximum to the minimum } calculated 30 days fot u.ing LOCA. .i s 1 1 la J .4a i J
c,- i, f 640.20 Verify operability of the solid and ] (14.2.12) liquid radw'aste systems CP-68.1r t P-69.1) by testing with representative l, chemical waste streams. Equipment and } systems' described in FSAR Sec t ion s 11.2 ' q t .} and 11.4 should be tested. The acceptance I criterion for the solid radwaste system should require that there be no free i liquid in the solidification sample. 640.21 Provide a description of a test which j (14.2.12) demonstrates that the MSIV-LCS components ~ operate properly Jhen handling steam nd i that the system can handle the amount of leakage that is pr7esent when the main steam system is at operati'ng temperature. 640.22 We have noted on other plant startups that (14.2.12) the capacities of main steam relief valves (SUT-22) and turbine bypass valves (SUT-23) i t are sometimes in excess of the values i assumed in the accident analyses for inadvertent opening or failure of these i i valves. Provide a description of the 5t j testing that demonstrates that the capacity .} of these valves is consistent with your accident analysis ' assumptions. 1 s 9 i
640.23 Expand the Remote Shutdown System Test i j (14.2.12) (SUT-24) to address Regulatory Guide 1.68.2, " Initial Startup Test Program to Demonstrate Remote Shutdown.. ( Q Capability for Water-Cooled Nuclear
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i Power Plants," Regula. tory Positions 1l C.1-4. 640.24 Modify the Turbine Trip Demonstration l I l (14.2.12) (SUT-25) or provide abstracts of other l 'i tests that demonstrate that both turbine ) l 'l throttle valves and main generator breaker l trips are conducted at full rated poweri ~ i i or provide technical-justification that i .l shows how the test purpose can be met j without accomplishing both' full power i i
- j trips.
,' l A sufficient technical justi*ication would 'l 8 be if the turbine trip is initiated directly 'i I by all remote-ma'nual openings or automatic t j trips of the generator main breakers i.e., a direct electrical signale not'a secondary i turbine ove_rspeed. The effect such as ,{ method used for opening the main generator I breakers (by simulating an automatic or 6
l [L 5 1 manual trip) should be selected such that t the turbine generator will be subjected to the maximum credible overspeed condition. 640.25 It is the staff's position that the 4 1 1 (14.2.12) Recirculation System Trip Demonstration (SUT-27) includes a two pump trip initiated from approximately full rated power. Your FSAR should commit to a two pump trip and .]
- s provide acceptance criteria for this test
.) ,l or justify that a two pump trip is not a credible event. This,justificationi if j shouldconshderbothlossof ,) providede 4 4 offsite power and a single human error j during all surveillande tests or maintenance activities that will he~co'nducted or allowed during plant operations. Confirm that the i test is conservative with respect to assumptions made in Chapter 15 of your FSAR and provide stabitity criteria for process j variables following planned trips. 5 Alsoe (a) provide acceptance criteria for a j speed of the recirculation _nump (following 1 trip of the normal supply breaker) when the j
.... t LFMG set breaker closesi (b) provide acceptance criteria for pump startup rates that are consistent with assumptions of FSAR Chapter 15, and O (c) describe hov you will verify that no cavitation occurs at allowable pbwer and flow conditions. 640.26 Expand your preoperational and startup (14.2.12) test descriptions to describe (or cross-reference other appropriate FSAR Subsections) all expansioni vibratione and restraint testing prescribed by NUREG-0800 (Standard Review Plan) Section 3.9.2.I.1, and snubber-2 testing prescribed by Section 3.9.3. ~ 640.27 Modify Figure 14.2-1 to ha've the notes (14. 2 ) subsection refer to$the correct accompanying figure (1) The first note should refer to Figure 14.2-6, not Figure 14.2-5 The second note should refer to Figure (2) 14.2-7, not Figure 14.2-6 (3) The third note should ref er to F'i gu r e I 14.2-5, not F i gu r e 14.2-7. -i i L i i
2 't 640.28 Modify the test titles shown in Figure (14.2.12) 14.2-5 for SUT-25, SUT-35, and SUT-36 to correspond to those of Table 14.2-3. 640.29 Provide a test description for eny (14.2.12) Confirmatory Inplant Tests of Safety-Relief ~ Valve Discharges to be performed i n" i compliance with NUREG-0763. b ,f i b e e 8 9 O e
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ERRATA , r. .l Section Page
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"4.2.6" should be ~ 14.2.6 14.2-14 "14.2.6". i Table Page Test ~ ,i 14.2-3 7 SUT-11 "Are the same" should be "Are in the same" t (Acceptance Criteria, [l 1 'b.1)
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ii SUT-12 " System Performance" t l should be " System Per- '} 1 formance Verification" i 1 4 I (Title) i 12 SUT-20 " steady-state greater" 4 ~ I ,,should be " steady-state i i condition greater" )* (Prerequisites) 1 I 1 19 SUT-35 " Steady State" should i be " Steady-State" (Title) 14.2-4 6 P-18.1 " P18.1 " should be ( P-18.1 ) " (Title) t 8 P-24.1 "Vage" should,be " Voltage" (Acceptance l Criteria a.) 24 P-59.3 " relief values" should l l. be " relief valves" I ! (Test Method) 'l I 4 i
W= J 1 Figure 't Supresion Pool" 14.2-7 should be " Suppression ) Pool" j "Hydratics" should be "H y d r a ttl i c s " ~ "99.11" should be "9 9.1 " l ( i 4 e e me eW i 1 i 1 I i i + j ) I i i I ( ( l 1 1 'I 9}}