ML20140B719

Forwards Info Re 841018 Request for Deviation from 10CFR50 App R,Section Iii.G to Install RCS Cold Leg Temp Instrumentation in Auxiliary Control Room.Request for Deviation Re Annulus & Containment Areas Withdrawn

ML20140B719
Person / Time
Site:	Sequoyah
Issue date:	03/19/1986
From:	Gridley R TENNESSEE VALLEY AUTHORITY
To:	Youngblood B Office of Nuclear Reactor Regulation
References
NUDOCS 8603240299
Download: ML20140B719 (23)

Text

{{#Wiki_filter:. _ ~.. - _. e s TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 SN 157B Lookout Place March 19, 1986 i Director of' Nuclear Reactor Regulation Attention: Mr. B. Youngblood, Project Director PWR Project Directorate No. 4 Division of Pressurized Water Reactors (PWR) Licensing A U.S. Nucleer Regulatory Cotanission i Washington, D.C. 20S55

Dear Mr. Youngblood:

In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 j As part of our response regarding compliance with Appendix R to 10 CFR 50 that was submitted to NRC by the October 1, 1981 letter from L. M. Mills to E. Adensam, we requested approval of an exception (deviation) to the requirements of Section III.G of Appendix R for the annulus and containment areas of units 1 and 2 of our Sequoyah Nuclear (SQN) Plant. This request is hereby withdrawn as we plan to perform modifications to install additional sprinklers and detectors in the annulus areas of both units and minor fire barrier sealing inside primary containment for each unit in accordance with Section III.G. By the October 18, 1984 letter from J. A. Domer to E. Adensam, we requested a deviation to the requirement to install reactor coolant system (RCS) cold leg temperature (Teold) instrumentation in the auxiliary control room for SQN. For the Watts Bar Nuclear Plant, additional information was submitted to NRC by the September 26, 1985 letter to E. Adensam from J. A. Domer. This same i information is considered applicable for SQN and is enclosed for your consideration of our deviation request. If you have any questions, please call Jerry Wills at FTS 858-2683. Very truly yours, j-TENNESSEgVALLEYAUTHORITY l . 4. &x . Gridley Manager of Licensing Enclosure 1 cc: See page 2 B603240299 860319 b PDR ADOCK 05000327 F PDR g An Equal Opportunity Employer ~-

~2-4 Director of Nuclear Reactor Regulation March 19, 1986 cc (Enclosure): U.S. Nuclear Regulatory Commission j Region II Attn: Dr. J. Nelson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. Carl Stahle Sequoyah Project Manager i U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 I t i i l f s t vn e ~

h l e Justification for Use of T-sat to Approximate T-cold in the ACR

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N.".~ As discussed in TVA's letter to NRC dated June 17, 1985 TVA has provided =- adequate instrumentation in the auxiliary control room (ACR) to safely shut down and cool down the plant during conditions of main control room (MCR) i f uninhabitability. . i., .t 1 i 1, Due to NRC staff concern about use of steam generator pressure to obtain Da saturation temperature to infer RCS cold-les temperature, TVA agreed to g provide additional information. Attached are discussions on operator training, uses of steam generator pressure indication, cost estimate for i

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) h$ adding T-cold to the ACR, and Sequoyah and Diablo Canyon natural circulation - p 4.n test data. 3 (f. ' 1 A h,,7 Any discussion conceming the adequacy of instrumentation in che ACR must be f preceded with a discuccion regarding the requirements placed on that F;/: instrumentation and the conditions under which it will be used. ,d(, ' The ACR is designed to safely shut down and cool down the plant to cold shutdown M.x ? 0 (200 F), under conditions of MCR evacuation. This situation is postulated i 85-to exist due to a fire in the control building. According to 10 CFR 50 (,-N. ' Appendix R, this postulated fire occurs in only one location (in this case, an G,$ area of the control building) and is not coincident with, subsequent to, or .;J,.'I preceding any other design-basis event. TOO @7 postulated to exist coincident with the fire.A loss of offsite power is, however, Thus the plant shutdown and subsequent cooldown is simply a natural circulation cooldown via heat transfer to the steam generator and subsequent steam release via the steam generator gg atmospheric relief valves. This process takes place until approximately 9%. 3500F and 380 psig are reached in the RCS. , h,*.'..3 At this point, the residual heat removal system is placed into service and provides forced circulation for the _h@:.T.f remainder of the cooldown to cold shutdown conditions. $Ma", The discussion of the adequacy of T-sat versus T-cold centers around the s$ff[O cooldown from hot standby to 3500 F. During this cooldown, RCS T-cold is j f 'p determined from S/G T-sat and is used for two purposes:

1) along with RCS 1

PM,' hot-les temperature to indicate adequate natural circulation, and 2) to ensure J.[*] the cooldown rates are maintained within the plant cooldown limits required by j Q' ff 10 CFR 50 Appendix G. As shown in the attached data from Sequoyah and Diablo Canycn (see figures 3 through 8) T-sat and T-cold track together extremely i Well between hot standby and 3500 F. In fact, at most points they are i tracking well within the error tolerance on a wide range T-cold indication i loop. instrumentation) will inherently lag behind core conditioAny indication of ns due to delayed fluid transport time under the low flows. This time las occurs for both d',' direct T-cold and T-sat via steam generator (S/G) pressure indications. This N sort of degrading condition would not result in any adverse conditions before l r l 3

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de. a 'e Justification for Use of T-sat to Approximate T-cold in the ACR (cont) , L. 'jn .-d it is detected 'by exist 1ig instrumenta. i'on.4.. l . t - Thi.., ' ition,wo'u.ld-b_el "p socond. q y. E [detectedbyRCSloopdifferentialtemperaturesonboththegoodloopsand the degrading. loop and secondary side indications such as,S/G levels and .y%' auxiliary;feedwater flows. # As shown on the attached gecphs (see figure 1 9[ through 8),' T-sat is almost always a few degrees below T-cold and thus T-sat will result in the most limiting (and thus more conservative) 'r cooldown rates. m.- a < > 9. - The ability:of'the' ope _ratorsito adequately,~us,v/G pressu_i, ndication' to r, ~ .a_- ~; m ?g eS re [nfeFT-cold'ss'beeridemonstrated during h5t functional testing at 2 Bar unit ~1 and startup testing;at ~Sequoyah unit:1'.~ Additionally, rel Waits M;h.Q. actio'ns have increased'tiie"already high,levey of confidence in this area: 2' C cent

1) Watts Bar operators have again walked'through the procedures pertaining,

i , ar.: s g.g;, to' shutdown /cooldown from the ACR, and 2) Watts Bar is in the process of adding a dual scale to the S/G pressure indicators to allow direct reading g 9+. gg 7_,,g,. .u.. cn. w _.ua.., _ :.g. au:. 2n u. e = 3e Ja E E ' _ * / .u ;Uh _ u ; re ;27^ :

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+: h' py;. 'gff;,. In, conc.lusion.,. TVA believe a:slit-has provided sufficient indication in the ", ~

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ACR to safely shut down and' cool down the" unit under conditions of MCR 'h. 'l uninhabitabilityi ;Thus',"the requirements of,10 CFR,50 Appendix..R'7. y ~ '47.7 section-III item L.2;d have been met. ~ TVA cannot ju' tify on a rcost-benefit 'Qc basis the additional $160,000 ^ s 7.1 provide RCS T-cold instrumentation in the ACR.per unit (initial iristallation costs only) to . :,r..:. ~ ~ ...::._a a., uo:o.". 3,.- F ~ 0ali.h G ;O L '! 1 i OOir.C [.d0f t b'[ LI. C.,C [ 1 '.* C. R u ;., I.h u ; '.snt OlYltOO%Ta and

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E, n A. Impact of Operators Using T-sat .}.... Each licensed operator receives a minimum of 40 hours of claisroom %4 1 training covering heat transfer, thermodynamics and fluid ftow. l. i Each shif t technical advisor has 80 hours classroom training cove ring heat transfer, thermodynamics, and fluid flow in addition to the r yM undergraduate studies in this area. Sh This training provides the operators with knowledge of the'modynamic G E ? 7. principals such as saturation pressure and temperatures. This G '.1 knowledge is reinforced in simulator training where subcooling margin h.{. calculations and RCS cooldowns using the atmospheric relief valves require saturation pressure and temperature manipulations. Qi.' dgy., Abnomal Operating Instruction-27 (AOI) covers main control room J.jtC, inaccessability. Operators have recently completed another y f(Z. walk-through of this procedure to ensure familiarity and confidence in hy.*? S-execution of this AOI. Additionally the AOI refers the operator to 'gj f, Emergency Instruction section ES-0.3 for natural circulation cooldown 'yy/7 guidelines. .:i$ The AOI specifically instructs the operator to use S/G 21' pressure-to-temperature conversions for T-cold. '4'.!jj As an added human factor enhancement, a dual scale will be added to the WI S/G pressure indicators in the ACR. This second scale will read p[;$,~ saturation temperature and thus allow the operator to infer T-cold without the use of steam tables. E This is similar to the dual scale M'l

• used in the main control board (M-5) on RCS pressure to provide a corresponding saturation temperature for subcoolin6 margin calculations.

This dual scale will be in place by initial entry into .hg.e mode 3. 'd,j;p '- 'A - .N-In summary, Watts Bar operators and shift technical advisors are %',F trained in the theory and use of T-sat / saturation pressure (P-sat) 'if,C calculations. TVA believes the negative impact of the operators p;;g[p,;g utilizing S/G pressure conversion to saturation temperature is negligible. Additionally, the incorporation of a dual scale to allow 4g i the operator to directly read saturation temperature will greatly py[ reduce the response time and completely eliminate conversion errors. hbf'.*, ~ .g -v. P-e. %gy N f{ - :.e,; 1s .a.y. - 7s-A s .e y .5 N.h."]

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B,. Benefits That S/G pressure Indicators Have Versus RCS Wide Range Cold-Lex Temperature Indicators E Ah 1. s.?nr;d op 3r nar receim 1 n wirirl of 40 hO*.!CC J f F. i?. M T An ACR.has-always been a:Partnof the-TVA design. aThetpurpose of the ? ACR.is to. safely _ shut down;and cool: down..the plant to cold -shutdownn under: conditions :of MCR evacuation. u

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7.'. TheAsignobjectivewastoprovidethiscapabilitywithinthe f ' ;. constraints of space availability and-design complexity. Where !jgf possible equipment was. chosen to meet:several needs.- n e tc ~,c i:: rd nf;cced in sinnlater trnini r Vc.cra cch.ml b : -rh l '.. T-cold; indication in the ACR has a' limited use.. ~ For all practical purposes.it hadtonly two functions:

1) in conjunction with T-hot to verify the presence of natural circulation, and 2) as one method to unsure compliance with plant cooldown limits. T-cold indication was i

J. not, included in.the original. design.. requirements'for the:ACR. It was determined to not be necessary since it could be inferred.from S/G. ,F pressure indication. 'r

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t,_, um < mue t % ~ 2 D:2.~1 =_:. :a * - -' ' % M ~ r* ' r; S/G pressure indication,ehowever, has many uses: mm T.' . :..z;, v -4 e u.c;

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1) Verify proper operation of S/G atmospheric relief valves (S/G ARV) mcontrollers used'to cooldown from the-ACR. a u .a

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3) :t. Identifies. approach to: S/G : pressure:: limits /safetyavalve. lif Ling.

cocc~powliw; e,n.ucatien terporature t'ce mtco:s i irr f ( 4)1e:S/Gipressuresis an:inputato thes u r3in steamline delta:pressuretsafetyc rc x injection signal. Thus, indication of symmetries S/G cooldown/ depressurization is important to prevent inadvertent actuation. v(Although the equipment with control transferred to;the ACR will R

-not automatically actuate.)

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.s mm mu n-. 2 r.. 5). ;And of course, can be used to determine RCS. cold-leg-temperature. u -: .sr w: 1.,: w -- W ..::n. w.w to In summary,- S/G pressure indicationnisma vital. component;of;a tl -wa controlled cooldown from the ACR, whereas T-cold. indication has-essentially only two uses (both which can be approximated by S/G - Pressure). the original design of the ACR was sound.Thus, TVA believes the decision to n C. Detailed Cost Estimate of Installinz T-cold Indication in the ACR TVA has prepared detailed cost estimates for installation of RCS wide P range cold-leg temperature indications in the ACR for unit 1. Unit 2 costs would be somewhat lower if work could be scheduled prior to that unit's fuel loading. Total cost for unit 1 = $163,618.00 Design costs = $ 42,000.00 (* Construction costs = $111,139.00 QA costs = $ 10,479.00 l l l l

c., It should be noted that the $163,618.00 only includes initial installation costs, it does not include the routine maintenance, required surveillance testing, or replacement costs over the 40-year life of the plant. Historically, TVA has estimated these additional expenses to at least equal the original cost of the equipment insta11agion. ' {., D. Steam Generator (S/G) Stratification Data i~ Effects of potential S/G stratification during S/G isolation or reduced [i" steam / feed flow rates around Residual Heat Removal (RHR) System cut-in

G conditions should be considered as to their effects on T-cold. T-sat relationship. During TVA's Sequoyah Nuclear Plant's initial startup testing program, special test number 4 (ST-4) was run.

This test completely isolated two S/Gs. As shown in the attached graphs (figures 1 and 2) actual T-cold and S/G T-sat track very well. This is

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important when considering that under these conditions, S/G T-sat would yi-be utilized in conjunction with T-hot to identify loss of natural circulation in that loop. The data shown is applicabic for lower temperatures since the nominal temperature of the isolated S/G would not affect the response. Additionally, figures 5, 6, 7, and 8, which show the Diablo Canyon natural circulation test data, show that at steam / feed flow rates at RHR cut-in ( es 350 degrees F) conditions T-cold and S/G T-sat continue to track very well. Since the enthalpy rise of'the auxiliary feedwater to saturated steam condition is essentially the same at 500 degrees F { and 350 degrees F (RHR cut-in conditions), the only effect on steam / feed mass flow rates is the amount of decay heat generated. l Normally, decay heat will decrease to one-half between post teip conditions (1 hour after trip) and the time necessary\\to reach hot-shutdown conditions (RHR cut-in conditions - at the most 24 hours). Thus, the most the steam flow / feed flow rate will decrease by is one-half. This is still a substantial feed / steam flow rate and would not result in any appreciable S/G stratification. E. Sequoyah Natural Circulation Test During Sequoyah Nuclear Plant's initial startup testing program, special test number 9B (ST-9B) was run. This test demonstrated exceptable boron mixing and cooldown capabilities during natural circulation. throughout the test, T-sat tracked T-cold very well.As shown in the atta F. Diablo Canyon Natural Circulation Test In order to reinforce and validate the test data -from Sequoyah bar requested T-sat and T-cold data from the recent Diablo Canyon , Watts i natural circulation test. of that data for all four steam generators. Attached are graphs (figures 5, 6, 7, and 8 T-sat tracked T-cold extremely well down to about 3000 C' (RHR) was put into service. F when residual heat removal system ~.

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