ML20024G869

Proposed marked-up Tech Specs,Including Page 3.8/4.8-5 & Table 4.8.1

ML20024G869
Person / Time
Site:	Monticello
Issue date:	08/20/1971
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20024G867	List: ML20024G866 ML20024G868 ML20024G869
References
NUDOCS 9105010227
Download: ML20024G869 (37)

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Mik' h:$l',**!;.;h.{g.g ~:g_ 4. =? c; .: p ' ',3 v A S,;~f x [' .. v -' - ? t. Oc:, y, , :.. -- ~ o,, s .y g y...., ~ ; c.. 3 ~ I '. ? p hibit B - Continued 30 LIMITInc conDITIoD3 FOR OPEPJtTION 1+. 0 SLEVEILLAliCE BEQUIRDIEITfS u o.o c. Isotopic analyses including detemination cf tritium of a representative batches of liquid 0 3-effluent chall be perfomed and recorded at least once per quar-nru ter. Each batch of effluent

• 4 releaced chall bc counted for 7,

gronc alpha and beta activity 00 and the results recorded. At u80 leact once per month a ga-m @y0 cean of representative t,atches (J of effluent cnall be perfJrmed and recorded to detemi."e the camaa energy peaks of there batchec. If energy peaks other than those determined by the previous isotopic analyses are h found, a new cet of isotopic ernlyses shall be perfomed and recorded. d. Grab camples will be taken from the discharge canal monthly and analyzed for tritium and signi-ficant icotopes. e. inuid effluent a monit-4 ruted s' C uarterly. Og I.e te 1 .Da [, i 3.8/1.8-5 172 4 i i

" M M UH M 5;x ~~ ,..f - b? ?. - ' -u. . ~.. Eihibit B - Continued 1 r. [ 1 1 Table 4.8.1 SAMPLE COILECTIOII AIID ANALYSIS l fiOIEICELLO liUCLEAR PLAIE - EI:VIROIIMEIRAL MOUITORIIIG PROGRA Collection Sa:ples itnalysis ) Type of Sample Tyne of Ar.alysis Collection Site Frequency Pcr Year Per Year ~ River Water GB, GS Upstream 600 ft. from in-Weekly 156 328 H3 (M), SrW (Q) take canal. Dcwnstream 600 ft. from discharge canal. St. Paul raw water intake. Lake Water GB, GS S local lakes Ifonthly 72 288 H-3, Sr-90 1 control lake Well Water GB, GS 6 cites within 5 miles Quarterly 24 96 H-3, Sr-90 of plant site including the Ibnticello Well. Precipitaticn GS, GB, H-3 Meteorological Station Monthly 24 120 I I-131, Sr-90 Plant site. State Health Dept. Bldg.- Mpls. Lake and River GB, GS 5 local lakes, 1 control Semi-annually 16 64 [ Ecttom Sediment Sr-90, Cc-137 lake. Upstrean of plant. Downstream of plant. Plankten, Algae GB, GS 5 local lakes, 1 control Quarterly 32 128 L or Insects Sr-90, Cs-137 lake. g 4,lg) -p; Upstrean of plant. Dwnstream of plant. p! 174 k'< < 3.8/4.8-7 r. {-.

y.: :, _ . s * ~ ~ ~ . gl ~' . !;a: }g%. l Table '4.8.1 Continued r Collection Samples Analysis Type of Sar.ple Type of Analysis Collection Site Frequency Per Year Per Year Aquatic GB, GS 5 ?ocal lakes, 1 control quarterly 32 128 h Veget.ition Sr-90, Cs-137 lake. gy y/,p,) Upstream of plant. t Downstream of plant. Clams GB, GS Upstream of plant. Quarterly 8 16 Downstrean of plant. (When avail-able) Fish GB, GS Upstream of plant. 8 16 (Q(uarterlyj//, % 4,' Q I, } Downstream of plant. Milk GS, I-131 Two farms / region, four Mohthly 96 384 Sr-90, Cs-137 regions. .' 3 l>* Topsoil GB, GS From 3 fields downwind of Semi-annually 12 48 Sr-90, Cs-137 plant site, also 3 fields irrigated with river water downstream of plant. l., Vegetation GB, GS From 3 fields downwind of Semi-annuan y 6 18 b I-131 the plant site. Agricultural GB, GS, I-131 From 3 fields irrigated Annually 3 15 Crops Sr-90, Cs-137 by river water down-(at harvest) stream from the plant.

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s 3 n: ; g e. .4 8 \\ ,e c phibit B - Continued J l 4.0 SLEVEILLAIICE REQUIRE 45!TS 30 LIMITII!G COIIDITICII FOR CPERATIOI; g l 2. E3th diesel Eenerators are operable and capable of feeding their designated 4100 volt buses. A second cource of off-cite power (reserve 3 tninsformer LAR) is fully operational and energized to carry power to the plant 4160V ac buses. h, (a) h1(,07 Buces #15 and #16 are energized. (b) t807 Load Centerc $103 and #104 are energized. 5 All ctation 24/48,125, oni 250 volt batteries are charged and in cervice, and atrociated battery chargers are operable. O When the made switch is in Run, the avail-I B. ability of electric power chall be as speci-fled in 3 9. A, except as cpecified in 3 9.E.1, 3 9.b.2, 3 9.P.3 and 3 9.E.4. o r 74r r << h cc IS Sbu Yl#~ '" Slwll br pha.( 12 a o 1. Transmission Lines Frem and after the date that inecming power is available from only one line, reactor operation is perniccible cnly during the succeeding seven days unless an additicnal line is cooner placed in t 181 39/4.9-2 -=~w* e -m- -w - a

5 Y fh h?f h i - )4 4.0 SURVEILINICE R$UIRDGIITS 30 LIMITING CONDITIONS FOR OPERATION c. During each refueling outage, For the diesel generators to be. c. the conditions under which the considered opemble, there. shall be a minimum of 26,250 gallons of diesel diesel generators are required will be simulated and tests con-fuel (7 days supply for 1 diesel Cen-ducted to demonstmte that they f erator at full load) in the diesel will start and be ready to accept the oil stomge tank, emergency load within ten seconds. d. During the monthly generator test, the diesel fuel oil transfer pump and diesel oil service pump shall be operated, Once a month the quantity of e. diesel fuel available chall be logged. f. Once a month a sample of diesel fuel shall be taken and checked for quality. s 4. Station Battery Systems 4. Station Eattery Systems if Every week the specific gravity f a. .s e r ' cas - ?- > n one of the and voltage of the pilot cell two 125 V battery systems or the 250 V and temperature of ad,Jacent cells battery system is made or founl to be and overall battery voltage shall inoperable for any reason,]r^1 '^- q te reasured. L.. i., p pyQl: ^^!; 1 .. g  : _-m- -* n.. m m.; pct t;tt-:.j I c:: w. l v - -* am on/ul y 5 4 Jifo~ oF 71, r<aL w;tt (,, ak wah Llf~;bef a,,/ k ra 183 3.9/4.9 h t a,,,,wata s ina lt % r fu a,.! L less 7hn 212 0 f unik; JY N' h o u,e s u a los S .s.a e It & lhry QS M Son v ka/s 97 sve S /s. h

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l Exhibit B - Continued ,~ Bases Continued 3.6 and 4.6: D. Coolant Leakage The fomer 15 gpm limit for leaks from unidentified sources was established assuming such leakage was canirg frmi the primary system. Tests have beta conducted which demonstrate that, a relationsliip exists between the size of a crack and the probability that the crack will propagate. Frcs the crack size a leakage rate can be detemined. For a crack size which gives a leakage of 5 cIra, the probability of rapid propagation is less than 10-5 lhus, an unidentified leak of 5 gp:n when assumed to be fran the primary system had less than one chance in 100,000 of propa-gating, which provides adequate margin. A letkage of 5 cpm is detectable and teasureable. The 24 hour period allowed for determination of leakage is also based on the low probability of the crack propagating. The capacity of the drywell surp pumps is 100 cpm nr.d the capacity of the drywell equi;rsent drain tant pu=ps is also 100 gyn. Femoval of PS cpm fran either of these cumps can be accatplished with considerable margin. The perfomance of the reactor coolant leakage detection system, including an c ealuation of the speed and sensi-l tivity of detection, will be evaluated during the first 36 months of plant operation, and the conclusions of this evaluaticn will be reported to the AEC. Modifications, if required, will b-perfome i during the first refueling outage after AEC review. In addition, other techniques for datectitu; leaks and the applicability of these techniques to the Monticello Flant will be the subject of continued stud. i E. Safety and Felier Valves Experience in safety valve operation shows that a testir.g of 504 of the safety valves per refueling outage is l I adequate to detect failures or deterioration. A tolerance value is specified in Section llI of the A31E Boiler and Pressure Vessel Code as +1% of design pressure. An analysis has been perfom-d which shows that with all safety valves set 1% higher than the set pressure, the reactor coolant pressure safety limit of 1375 psic is not exceeded. Safety /relier valves are used to mini;nize activation of the safety valves. The operator will set the pressure settings at or below the cettings listed. I:cwever, the actual setpoints can vary as listed in the basis of Specification 2.4. ,I i k.epenYeel bY J .e opr at c wil .et the pre-m settir-a or in sw tn se .nc li-m. s as li in the tm of Speci _ tion 2.4. con -

• The required safety valve steam flow capacity is detemined by analyzing the pressure rise accanpanying the main steam flow steppage resulting from a turbine trip initiated with the reactor at 1670 Wt.

The analysis assumes no steam bypass system flow, no turbine valve trip scram, but a reactor scra:r frmt indirect means (high flux). The relief and safety valve capacity is assured to total $0% (35% relief and 15% safety) of the full power l steam generator rate. This capacity corresponds to assuming that three of the four relier/ safety valves (35.4%) and two of the four safety valves (18 5%) operated. For additonal margin three safety and three safety / relief valves are required to be operable. 3 6/4.6-20 134

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14

~ ^ ~ ^ ~ ETHIBIT A %,sg. MONTICELID NUCLEAR GDIERATING PLANT DOCKET NO. 50-263 f(,4 '. PROPOSED CHANGES TO TECHNICAL SPECIFICXrIONS [r" APPDIDIX A 0F PROVISIONAL OPERATING d4-LICDiSE NO. DPR-22 7 w% d I'2 l ' ;Q g mm a O,y'+p p 9, ( q 1. Page i, Item 3 2 and 4.2, C %,A Change to

• Qg "'

Q" C. Control Rod Block Actuation N p*, Renson for Changes

• J' The word " Block" was an omission in previous submittals fe y

2. Page 11, Jtem 3.4 and 4.5 Change to: W 3.5 and 4.5

• • • • • • *'Lu ~..S t?$

nf j 3. Puel Claddint? Interrity Safety Limit Nh Page 7, Item 2.1 B, Change to read M When the reactor pressure is less than 600 peig or core flow is less than D{ 5% of design, the reactor thermal power transferred to the coolant shall not exceed 300 MW. Page 10, Figure 2.1.1 ,s N, Enend the two curves linearly from the present termination at 25% to 5% 7.- at 18% thermal power (300 MW). JF Page 15, Basse: 2.1 4 Change the first two sentences of the last paragraph to read: The range in pressure and flow used for Specification 2.1. A was 600 psig to 1250 psig and 5% to 100% flow respectively. Specification 2.1.B pro-Al - vides a requirement on power level when operating below 600 psig or 5% t. 4'

flow, w

0 Reason for chance: y f,.. ~ The basis given for fuel cladding integrity safety limits applies to the lower core flow limit of 5% but with less cargin than the current lower p limit of 25% flow. Following recirculation pump trip test at Monticello, y the operating point was found to be close to the 25% flow limit line. The change vill decrease the chance of a " technical" violation of the - 3b', specification and vill cale the safety limit curve consistent with curves [j[ presently in use at other facilities. S4.*Pages20,21,22,and26 These pages refer to deviations diccussed on Page 22. The deviations are m y 'qs discussed on Page 18, not Page 22. g.:

65. Page 30, Item 4.c on Table 3 1.1 V

Add " limiting Trip Setting" of13/125 of full scale. This was an omission f+ in previous submittals. )? l 6 t l = l h. '= =.-

ibit A - et. tinued\\ a,, [6 Page 39, Third paragraph y# Sign on 10% is incorrect, should be $ 10%. r i.. , <7. Page 51, Item 4 an Table 3.2.1 Change Item 4 to be as follows: Min. No. of Oper-i .s gs Total No. of able or Operating Trip Inst. Ch. Per Inst. Ch. Per Required 'g' Function Settings Trip System Trip System (1,2) Conditions 6l 4. g,CI Steam Lines a. HPCI High $150,000 2(4) 2 F f" Steam Flow lb/hr with N s60 sec I / time delay II-b. HPCI High 6300,000 2(4) 2 F .n Steam Flow lb/hr

1 c.

HPCI Str. I 200 F 16(4) 16 F Line Area High Temp. e e Reason for change On HPCI initiation, initial steam flow surges cause instrumentation indica- }g tions in excess of the current trip setting of 150,000lb/hr. Testing of this aystem has shown that normal steam flow indications are reached within 1 60 seconds after initially exceeding the 150,000 lb/hrtripsetting. The

5 trip setting of 300,000 lb/hr will provide steam line break protection J,

during the time delay period on the 150,000 lb/hrtrip. Wording in the current Technical Specifications is actually in error with the trip system o P" agreed upon with DRL and installed in the plant. This change corrects the

J-wording to be consistent with the existing trip system.

v; {8. Page 59, ** Allowable Bypass Conditions Change Item d. to read: W d. SRM Upscale block may be bypassed when associated IRM rance switches e are above Position 6. Reason for change: a

[;;

The SRM Upscale rod block is not necessary when the IRMs are above range 1. SRM Upscale rod blocks occur when IRM indication reaches the middle of range l 7. Allowing the block to be bypassed on range 7 will eliminate the need to r i' prematurely switch the IRMs to range 8. Also, additional margin will be provided to allow for possible f'iture changes in IRM and SRM calibration. [* Page 63, Not) (2) of Table 4.2.1 Change N)to (2) to read: Y Ly N ;j - ,e

O O W [n. Exhibit A - continued f'" ' Calibrate prior to normal shutdoun and start-up and thereafter check once per shift and tect once per week until no longer required. Cali-4 '. bration of this instrunent prior to normal chutdoun meanc adjuctment of channel trips so that they correcpond, within acceptable range and accuracy, to a simulated signal injected into the instrument (not pri-mary sencor). In addition, IRt! gain adjustment will be perforned, as nec?ccary, in the APFB/IF14 overlap region. T Reason for chance: The SRM and lh!i rod blocks are bypacced in the run mode. Calibration E can only be carried ac far as the instranent channel trip. The most accurate nethod of calibrating the IRM output signal ic by comparicon 2L, ' with the APRMs in the overlap region. t

10. Page 67, First Paragraph Change last centence to read ac follows:

l' 0 6 The trip settings of 200 F,1$0% of HPCI and 300% of RCIC design flows, and valve closure times are cuch that core uncovery is prevented and <{ fiscion product zelence is within 10 CFR 100 guidelines, b Reacon for chances b The trip secting for RCIC High Stean Flow listed on Page $1 is 1 h$,000 } lb/hr. Design steam flow is 16,$00 lb/hr maxh. The 150% trip cet-O ting referenced in the original draft was nennt to apply to the HPCI t systen only. q{i

11. Page 89, Iten h.h.A.2.b g

A, Change paragraph b to read as follows: ll b. Explode one of two priner accenblies manufactured in the cane batch w to 7erif/' proper function. Then inctoll as a replacenent, the cecond priner assembly in the exploci n valve of the systen tested p for operation. .c Reason for chance: At the tine unen thic specification was origirally discussed with the C AEC-DRL ctaff, it was thought that the two explosive charges accociated C, with each valve were independent devices which could be exploded indi-

• I vidually. Actually, the replacement charges come in the forn of a l

singla primer assenbly. The primer assembly contains two charges, either of which firing alone will result in valve operation. "xplosion of one priner accenbly is therefore the explosion of two charge'. The [ proposed change is consictent with specification h.h. A.2.a. which re-quires tecting of only one valve each operating cycle, and the present ? bases which states "A test of explocive charges from one nanufacturing ^ batch is made to assure that the replacenent charges for the tested Sycten are satisfactory." 4 - hp }- fl. W N/f

7;' e U U,ts Y s em hibi) A - continued F er 12. Page 92, Figaro 3.4.1 Continuo lower portion of curve to terminato at 10.8% at 2895 gallone. lomove limit of 11.4% at 22700 gallona. Rgnnon for chnnro: In one of the early draf t versionc of the Technical Specifications the Imtem portion of the curvo was removod to ascure that the required amotut of boron would bo injected within 100 minutes at a minimum flow of 2',' cpm. Subsequently, tra requirements were changed. The present opecification and bases requiro a minimum flow of 24 gpn and a pumping time not to exceed 125 minutes. Restoration of the lower portion of s the curve is consistent vit.h the present bases and will allow lower concentrations, thereby reducing mini =um temperaturo requiremento and reducing the posaibility of crystallization.

13. Pago 104, Item 3 5.D.3.a Change to:

a. The HpCI chall be capable of delivering 3,000 gpm into the reactor vosool for the reactor preocuro rango of 1120 psig to 150 paig. Rennon for chnnre: Design epocifications of 1135 pain to 165 pela were evidently miscal-culated to 1150 peig instead of 1120 poig, 1120 psig is the design value and sufficient overlap with maximum reactor preocuro in assured by setting the relief valves at 1080 poig chown $n Spoc. 4.6.E.2.a. 14. Page 134, Item 3.6.E Delete second paragraph. Roncon for chance: This wording is a repeat of last two centences in paragraph above.

15. Page 148, Item 4.7.B Correct outlining by adding 1 before paragraph beginning with "Standtri Cac--------- ".

16. Page 148, Item 4.7.B.l.b Change first centence to read as follows:

During each refueling outage prior to refueling, whenever a filter c is changed, whenever work is performed that could affect filter cycteac efficiency, and at intervalo not to exceed cix months botveen refueling outages, it chall be demonstrated that: Roncon for chance: As procently written, it requires filter tosto (DOP & Freon) during each scheduled secondary containment leak rate test. It has been interpreted that this mecns testing must be simultaneous with leak sto tooting. 6 This testing requirement la to demonstrate removal efficiency prior to ?, refueling operations and is irrelevant to simultaneous testing with the leak rate test. The tonting roanirement is satisfied with the proposed j dl(

• l g

wording. l ina L.s. 6 s, v : s'iJ ' l..

N" e e q E is' 7-s jr.ihibitA-continu:d,7_)x ( ) L v 1 P 5 g Also, we are required by Specification 4.7.C.1.b to perform additional secondary containment leak rate tests during the initial operating cycle zg under various wind conditions to enable valid extrapolation of leak rate test results. It is not desirable nor does it seem necessary to require k*7 the additional filter testing with the leak rate tests that are done for this reason. g. ?" 17. Page 149, Item 4.7.1.c 4' Correct sentence structure by adding and after removed. C

18. Page 150, Item 4.7.C.1 Delete paragraph a.

^ Reason for chance: These preoperational requiretents have been satisfied. Reletter and insert present paragraph e as paragraph a. 19. Page 150, Item 4.7.C.1 Add sipas before 4000 sefn in new paragraph a. Rencon for chance: This change still requires the original integrity but allows more flexibility in operation and testing. 20, Page 172, Item 4.8.C.2.e Delete this paragraph. Reason for chnnre: The requirements are a repeat from paragraph 4.8.C.1, page 171. 21. Page 174, Table 4.8.1 Add "When tvailable" to Collection Frecuency fer Plankton, Algae or insects. Reason for chance: These organis:s generally do not inhabit the river in abundance necescary to do radiological analysis. For example, no carples were available during the last quarter of 1970. 22. Page 175, Table 4.8.1 Add "When Available" to Collection Frecuency for Aquatic Vegetation and for Fish. Reason l'or chsnce: i Vegetation growth in the river in the area of the plant exists only during i part of the year. Fish sampling is limited to the middle of April to l about the first week in November which eliminates the vinter quarter l l sa=ple. 23. Page 181, Item 3.9.B l l Add to the sentance after 3.9.B.4 the following: "or the reactor shall be placed in a cold shutdown condition". Reneon for change: This was an omission in the previous submissions. 24. Page 183, Item 3.9.B.4 Change to read as follows: l

e f p, p J .'~ V \\ j " l.,* /* 'ThibitA-continued L-e1 $4 us.D4 4. Station 3attery Systems gj b If one of the two 125 V battery systems or the 250 V battery system is made or found to be inoperable for any reason, an orderly shutdown of the reactor will be initiated and the reactor water temperature shall '[ be reduced to less than 212 F within 24 hours unless such battery sys-e tems are sooner made operable. Rearpn for change The proposed change is more restrictive than existing requirements but is more consistent with intended cperation. ~ 25. Page 194, Figure 6.1.2 flormal Functional Organization Chart 4 Power Production and System Operation Add block for Vice President and change advisory function of the Saf ety Audit Comittee from Manager of Power Productinn and System Operation to Vice President - Power Production and System Operation. Recent title changes are also made on the revised Figure 6.1.2 in Exhibit B attached. Reason for change The change will make the organization chart consistent with the wording in the 6 1.E.1.e, Page 195. Page 196, Item 6.1.E.1. f.( 3) 26. Correct sentence by adding ands - - - the Vice President - Power Production and System Operation and the Manager of Power Production, with copies to the Plant Superintendent. 27. P.sge 203, Item 6.3.A Correct spelling of repetition in last sentence. 28. Page 210, !Jote (1) Change date of AEC Gaide to December 15, 1966. This later date is the current AEC Guide on Containment Testing. l j' - d p ft ? Q #

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f lErhibit B TABLE OF CON.2 a 1.0 DEFIIIITIONS 1.0-1 1 i 2.0 SAFETY LIMITS A'ID LIMITIIII SAFETY SYSTEtt SE'ITIDGS 6 I 1 2.1 and 2 3 Fuel Cladding Integrity 8 2.1/2 3-1 6 2.1 Bases 2.1/2 3-8 13 h' 23 Eases 2.1/23-13 18 2.2 and 2.4 Reactor Coolant System -Q 2.2/2.L-1 23 2.2 Eases 'o -i 2.2/2.h-2 2h 2.h Bases 2.2/2.h-b 26 30 LIMITING cor:DITIor:S FOR OPERATIOIT AITD h.0 SURVEILIJliCE REQUIFSGITIS 23 3 1 and h.1 Reactor Protection System 3 1/h.1-1 28 31 Bases 3 1/h.1-10 37 h.1 Eases 3 1/4.1-16 h3 3 2 and b.2 Protective Instrumentatio-3 2/h.2-1 h7 h A. Primary Containment Isolation Functions 3 2/h.2-1 h7 w B. Emergency Core /c Cooling Subsystems Actuation 5 3 2/4.2-2 68 Bloc P C. Control Rod Actuation 9 3 2/h.2-2 L8 4 b D. Air Ejector Off-Gas System ? 3 2/h.2-2 a.8 N

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!;or~al Oneration 3.L/L.L-1 88 l f B. Operation with Inoperable Requirer.ents 3.L/4.L-2 89 l C. Volwne-Concentration Requirements 3.L/L.L-3 90 3.L an1 k.L Bases 3.L/L.L-7 9h .[ .a and L.5 Core and Contain.*.t Coolin,- Syster.s 3 5/L.5-1 G6 A. Core Spray Syster 3 5/L.5-1 o6 14 LFCI Gubsystem 3 5/L.5-3 98 l l l C. rib Service '. at :r 3 5/L.5-6 lol l it l l 11 I I e .. 2r. .7_' .m ?* e i-3.,$

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