ML19210B473

Tech Spec Change Request 70 to DPR-50 Re Extension of Operation Limits Beyond Three Effective Full Power Yrs. Certificate of Svc Encl

ML19210B473
Person / Time
Site:	Crane
Issue date:	01/09/1978
From:	Herbein J METROPOLITAN EDISON CO.
To:
Shared Package
ML19210B471	List: ML19210B470 ML19210B473 ML19210B476
References
NUDOCS 7911080699
Download: ML19210B473 (21)

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e UIIITED STA"'ES CF A':ZRICA NUCLEAR REGULATCRY CCICIISSION IN THE MAT'"ZR CF DOCKET NO. 50-289 LICENSE :io. DFB-50 METRCPCLITA'I EDISCN CCMPA'."I Sis is to certify that a ecpy of Technical Specification Change Request No. 70 to Appendix A of the Cperating License for '~hree Mile Island Nuclear Station Unit 1, has, en the date given below, been filed with the U. S. Nuclear Regulatory Ccemission rrd teen served en the chief executives of Lcndenderry Township, Daup;in County, Pennsylvania and Dauphin County, Pennsylvania by deposit in the United States nail, addressed as follows:

I'r. '4eldon 3. Arehart Mr. Harry 3. Reese, Jr.

Board of Supervisors of Board of County Ccenissioners Londonderry Tcvnship of Dauphin County R. D.

1. 1, Geyers Church Road Dauphin Ccunty Ccurt Ecuse Middletown, Pennsylvania 17057 Harrisburg, Pennsylvania 17120 METROPOLITAIT EDISCN CCMP.CTY By /

l Vice President Dated: Januant 0, 1078 1565 283

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N 0?OLITAII EDISCN CC:E riY JERSEY Cr.IITRAL PC'a*ER & LIGHT CO:GriY kid PE:lliSYLVrIIA ELECTRIC COMPATI THREE MILE ISLEID iUCLEAR STATIC:I U:IIT 1 Operating License :ic. DFR-50 Docket :Io. 50-269 Technical Stecification Chansre Request :To. 70

'~ is Technical Specification Change Request is submitted in support cf n

Licensee's request to change Appendix A to Operating License ?Io. DPR-50 for Three Mile Island :Tuclear Station Unit 1.

As a part of this request,

proposed replacer.ent pages for Appendix A are also included.

ME"'RCPOLITM! EDISO:I COM'ORTf

/s 31 C

Vice President Sworn and subscribed to me this day cf M /, 1978.

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Ilotary Publie/

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in % NCv. Il 13,0 1565 284

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Three Idle Island Nuclear Station Unit 1 (TMI-1)

Operating License No. DPR-50 Docket No. 50289 Technical Specificatien Chance Request No. TO The licensee requests that the attached changed pages replace pages 2-3, 2-o, and 3-3h, through 3-36a and Figures 2.1-2, 2. 3-2 and 3.5-2A through 3 5-2H.

Figures 3.5-2I through 3.5-2M are to be deleted.

Reasons for Chanze Recuest The change is to provide new Technical Specification (T.S. ) limits for operation beycnd 3 EF?Y vhich are a result of the folleving:

1.

The mode of operation will be changed frc a rodded to a feed-bleed = ode for cycle h.

2.

The =aximum actual core tilt li=it vill be increased to h.925.

3.

The T.S. limits based on the Departure frcs Nucleate Boiling Ratio (DN3R) and Linear Heat Rate (L'IR) criteria include apprcpriate allevances for projected fuel rod bov penalties, and h.

The power spike penalty due to fuel densification was not used in setting the DNBR - and Energency Core Cooling Syste= (ECCS) - dependent T.S.

limits.

This change is required to comply with the requirements of TMI-l T.S. Sections 2.1. 2, 2. 3.1 and 3 5 2. h.

Safety Analysis Justifvine Chance Request The changes presented in the attached pages and figures are based on the TMI-1, Cycle h Relcad Report by 3 & W.

Section 5 discusses the change in the operational =cde from a rodded to the feed and bleed mode. This mode of Operation is not unique for TMI-l in that it has been used at the end of previous cycles and requires no plant modifications.

Basically, it means that no full length control rods vill be inserted into the core during steady state conditions with the exception of approximately 105 of one regulating bank. This small insertion is to ecmpensate for discrete changes in soluble boren and to acco==odate small temperature and load de:1nd changes.

Transient xenon reactivity effects are ecspensated by changing the soluble boron concentration.

1565 285

r s

The curve of Figure 2.1-1 is the most restrictive of all possible reactor coolant pu=p-=aximum ther=al power ec=binations show in Figure 2.1-2.

The curves of Figure 2.1-3 represent the conditions at which a mini =um DU3R of 1.3 is predicted at the =aximum possible ther=al pcuer for the number of reactor coolant pumps in operation or the local quality at the point of minimum DNER is equal to 22 percent, (3) whichever condition is = ore restrictive.

The maxi =um thermal power for three pu=p operation is 87.1 percent due to a l

power level trip produced by the flux-flow ratio (Th.7 percent flov x 1.08 =

80.7 percent power) plus the maximum calibratica and instrumentatien error.

The maximum ther=al pcVer for other reactor coolant pu=p conditions is produced in a similar =anner.

Using a local quality limit of 22 percent at the point of mini =un DNER as a basis for curve 3 of Figure 2.1-3 is a ecnservative criterion even though the quality at the exit is higher than the quality at the point of =inimum DU3R.

The DNER as calculated by the B&W-2 correlation continually increases fro the point of =inimum DU3R, so that the exit DN33 is always higher art is a function of the pressure.

For each curve of Figure 2.1-3, a pressure-te=perature point above and to the left of the curve vould result in a DNER greater than 1.3 or a local quality at the point of mini =um DNER less than 22 percent for that particular reactor coolant punp situation. Curve 1 is more restrictive than any other reactor coolant pu=p situation because any pressure /te=perature point above and to the left of this curve vill be above and to the left of the other curves.

REFERENCES (1)

FEAR, Section 3.2.3.1.1 (2)

FSAR, Section 3.2.3.1.1.c 1565 286 (3)

FSAR, Section 3.2.3 1.1.k 2-3

+

V THERMAL POWER 8.EVEL, 5

- 120

(-44.112)

ONBR LIMIT (112) 1 (44,112)

~~

ACCEPTABLE 4 PUMP OPERATION KW/FT'

-- 100 g,,FT LIMIT LI li

( 44,87.1)

-. 90 (87.1) 2 (44.87.1)

(-60.80)

ACCEPTABLE

-- 80 MW 3 & 4 PUMP OPERATION

-- 70

(-44,59.6)

(59.6) 3 80 (44.59.6)

(58.4,58.4)

(-49.2,49.2)

ACCEPTABLE 50 2,3, & 4 PUMP (49.2,49.2)

OPERATION

- 40 30

-- 20

-- 10 L

I f

f I

f l

t l

f l

-60

-50

-40 30

-20

-10 0

10 20 30 40 50 60 Reactor Power imoalance, i CURVE REACTOR COOLANT FLOW (la/nt) 1 139.8 x 106 2

104.5 x 106 3

68.8 x 106 CORE PROTECTION SAFETY LIMITS TMI-1, CYCLE 4 F i gure 2.1 - 2

r s

The power level trip set point produced by the power-to-flow ratio provides both high power level and lov flow protection in the event the reactor power level increases or the reacter coolant flow rate decreases.

The power level trip set point produced by the power to flow ratio provides overpower D:iB protection for all =cdes of pu=p operation. For every flow rate there is a maximum permissible power level, and for every power level there is a minimum permissible lov flow rate.

Typical pcVer level and lov flow rate cc=binations for the pu=p situations of Table 2.3-1 are as follows:

1.

Trip would occur when four reactor coolant pumps are operating if power is 108 percent and reactor flow rate is 100 percent, or flow rate is 92 5 percent and power level is 100 percent.

l 2.

Trip would occur when three reactor coolant pu=ps are operating if power is 80.7 percent and reactor flev rate is 7h.7 percent or flev rate is 69.h percent and power level is 75 percent.

3.

Trip would occu-when one reactor ecolant pu=p is operating in each loop (t tal cf two pu=ps cperating) if the power is 531 percent and eactor flow rate is h9 1 percent er flev rate is h5.3 percen. and the power level is h9 percent.

The flux /ficv ratios account for the maxi =u: calibration and instrumentation errors and the maximum variatien frc= the average value of the RC flev signal in such a manner that the reactor protective system receives a conservative indication of the RC flow.

1 Uo penalty in reactor coolant flow thrcugh the core was taken for an open core vent valve because of the core vent valve su veillance progra during each refueling outage.

For safety analysis calculations the maximum calibratien and instrumentation errors for the power level were used.

The power-i= balance boundaries are established in order to prevent reactor thermal limits frc= being exceeded. These thermal limits are either pcVer peaking Kv/ft limits or D:GR limits. The reactor pcVer imbalance (power in the top half of the core minus pcwer in the bottc=

half of core) reduces the power level trip produced by the power-to-ficv ratio ao that the boundaries of Figure 2.3-2 are prcduced. The power-to-flow ratio reduces the power level trip and associated reactor power /reacter power-imbalance boundaries by 1.08 percent for a One percent flow reduction.

b.

Pu=p conitors The redundant pump onitors prevent the mini =u: core D:ER fro:

decreasing belov 1.3 by tripping the reactor due to the 1 css of reactor coolant pump (s).

The pump =cnitors also restrict the pcVer level for the nu=ber of pu=pc in operation.

1565 2gg 2-6

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THERMAL POWER LEVEL, *,

__120

(-17,108)

(17,108)

__100 l

y

=y, ACCEPTABLE M2 = -1.0 4 PUMP

(-35.90)

OPERATION

-- 90 (35.90) l I

(80.7)

- ou I

CCEPTABLE 70 3 & 4 PUMP l

(-35,62.7)

OPERATION (35,62.7) l l

-- 60 l

(53.1)

-- 50 l

ACCEPTABLE 40

(-35.35.1)

(. 5.1) 0 RA 10N l

l

__.0 l

-- 20 o

o I

S

?

i T

7l

[

-- 10 ii n

2 l

E i

i i

,i i

i i

i i

i 60

-50

-40 20

-10 0

10 20 30 40 50 60 70 Reactor Power Imaalance, %

]}{}g PROTECTION SYSTEM MAXIMUM ALLOWABLE SETPOINTS FOR REACTOR POWER IMBALANCE TMI-1. CYCLE 4 Figure 2.3-2

s f. If a control rod in the regulating or axial power shaping groups is declared inoperable per Specification h.71.2., operation may continue provided the rods in the group are positioned such that the rod that was declared inoperable is maintained within allowable group average position limits of Specification 4.7 1.2. g. If the inoperable rod in Paragraph "e" above is in groups 5, 6, 7, or 8, the other rods in the group =ay be tri=med to the same position. Normal operation of 100 percent of the thermal power allowable for the reactor coolant pump ce=bination may then continue provided that the rod that was declared inoperable is maintained within allowable group average position limits in 3525 3 5.2.3 The worth of single inserted control rods during criticality are limited by the restrictions of Specification 31.3 5 and the Control Rod Position Limits defined in Specification 3.5.2.5 3 5 2.h quadrant tilt: Except for physics tests the quadrant tilt shall not exceed a. +h.015 as determined using the full incore detector system. b. When the full incore detector system is not available and except for physics tests quadrant tilt shall not exceed +2.825 l as determined using the minimum incere detector system. c. When neither incore detector system above is available and except for physics tests quadrant tilt shall not exceed +2.Ch5 as determined using the power range channels displayed on the console for each quadrant (out of core detector system). d. Except for physics tests if quadrant tilt exceeds the tilt limit power shall be reduced immediately to below the power level cutoff (see Figures 3.5-2A, and 3 5-2B. Moreover, the l power level cutoff value shall te reduced 2 percent for each 1 percent tilt in excess of the tilt limit. For less than four pump operation, thermal power shall be reduced 2 percent of the thermal power allowable for the reactor coolant pump combination for each 1 percent tilt in excess of the tilt limit. e. Within a period of h hours, the quadrant power tilt shall be reduced to less than the tilt limit except for physics tests, or the following adjustments in setpoints and limits shall be made: 1. The protection system reactor power / imbalance envelope trip setpoints shall be reduced 2 percent in power for each 1 percent tilt. 1565 290 3-3h

r 2. The control rod group withdrawal limits (Figures 3.5-2A,

3. 5-23, 3 5-2C, 3. 5-2D, and 3. 5-2H, shall be reduced 2 l

percent in power for each 1 percent tilt in excess of the tilt limit. 3. The operational imbalance limits (Figure 3.5-2E, and 3.5-2F) shall be reduced 2 percent in power for each 1 percent tilt in excess of the tilt linit. f. Except for physics or diagncstic testing, if quadrant tilt is in excess of +27105 determined using the full incore detector syste= (FIT), or +25 915 deter =ined using the mini =u= incere detector syste= (MIT) if the FIT is not available, or +23.0h5 deter =ined using the out of core detector syste (CCT) when neither the FIT nor :CT are available, the reactor vill be placed in the hot shutdown condition. Diagnesite testing during power operation with a quadrant tilt is permitted provided that the ther=al pcVer allowable is restricted as stated in 3 5 2.h.d above. g. Quadrant tilt shall be monitored on a minimum frequency of once every two hours during power operation above 15 percent of rated power. t-1565 291 3-3La

3.h.2.5 Control Pod Fositions Operating rod group overlap shall not exceed 25 percent +5 per-a. cent, between two sequential groups except for physics tests. b. Position li=its are specified for regulating and axial power shaping control rods. Except for physics tests or exercising control rods, the regulating control rod insertion /vithdrawal li=its are specified on Figures 3.5-2A, and 3.5-23 for four pu=p operation and Figures 3 5-2C and 3.5-2D three or two pump operation. Also excepting physics tests or exercising control rods, the axial power shaping control rod insertion /vithdrawal limits are specified on Figure 3 5-2H. If any of these control l rod position limits are exceeded, corrective =easures shall te taken i==ediately to achieve an acceptable control rod position. Acceptable control rod positiens shall be attained within four hours. Except for physics tests, power shall not be increased above c. the power level cutoff of 92 percent of rated thermal power unless one of the following conditiens is sacisfied: 1. Xenon reactivity never deviated more than 10 percent frc= the equilibrium value for operation at 100 percent of rated thermal power. 2. Xenon reactivity deviated more than 10 percent and is nov vithin 10 percent of the equilibrium value for operation at 100 percent of rated ther=al pcver and asy=ptotically approaching stability. 3. Except for Xenon free startup (when 3 5.2 5.c.2 applies) the reactor has operated within a range of 87 to 92 percent of rated thermal power for a period exceeding 2 hours in the soluble poison control mode. d. Core imbalance shall be monitored on a =ini=u= frequency of once every two hours during power operation above h0 percent of rated power. Except for physics tests, corrective measures (reduction of i= balance by APSR ovements and/or reduction in reactor power) shall be taken to =aintain operation within the envelope defined by Figures 3.5-2E, and 3.5-2F. If the imbalance is not within the envelope defined by Figures 3.5-2E, and 3.5-2F corrective =easures shall be taken to achieve an acceptable i= balance. If an acceptable imbalance is not achieved within four hours, reactor power shall be reduced until i= balance li=its are met. Safety rod limits are given in 3.1.3 5 e. 3.5.2.6 The control rod drive patch panels shall be locked at all times with limited access to be authorized by the superintendent. 1565 292 3-35

3527 A power map shall be taken at intervals not to exceed 30 effective full power days using the incore instrumentation detection system to verify the power distribution is within the limits shown in Figure 3 5-2G. Bases The power-imbalance envelope defined in Figures 3.5-2E, and 3.5-2F is based on LOCA analyses which have defined the maximum linear heat rate (see Figure 3.5-2G such that the maximum clad temperature vill not exceed the Final Acceptance Criteria (2200F). Operation outside of the power imbalance envelope alone does not constitute a situation that vould cause the Final Acceptance Criteria to be exceeded should a LOCA occur. The power imbalance envelope represents the boundary of operation limited by the Final Acceptance Criteria only if the control rods are at the withdrawal / insertion limits as defined by Figures 3.5-l 2A, 3 5-?B, 3.5-2C, 3 5-2D, 3 5-2H, and if quadrant tilt is at the limit. Ad-ditional conservatism is introduced by application of: a. huclear uncertainty factors b. Themal calibration uncertainty c. Fuel densification effects d. Hot rod manufacturing tolerance factors. e. Postulated fuel rod bow effects The Rod index versus Allovable Power curves of Figures 3.5-2A, 3 5-23, 3.5-2C, 3 5-2D, and 3.5-2H describe three regions. These three regions are: l 1. Permissible operating Region 2. Restricted Regions 3. Prohibited Region (Operation in this region is not allowed) NOTE: Inadvertent operation within the Restricted Regien for a period of four hours is not considered a violation of a limiting condition for operation. The limiting criteria within the Restricted Region are potential ejected rod worth and ECCS power peaking and since the probability of these accidents is very lov especially in a h hour time frame, inadvertant operation within the Restricted Region for a period of h hours is allowed. 1565 293 3-35a

The 2515 percent overlap be reen successive control roa grou., is allowed r sined the worth of a rod is lower at the upper and lover part of the stroke. Control rods are arranged in groups or banks defined as follows: Group Function 1 Safety 2 Safety 3 Safety h Safety 5 Regulating 6 Regulating i 7 Regulating (Xenon transient override) 8 APSR (axial power shaping bank) Control rod groups are withdrawn in sequence beginning with group 1. Groups l 5, 6 and 7 are overlapped 25 percent. Se normal positien at power is for group 7 to be partially inserted. l The rod position limits are based on the cost 'i g of the f011cving three criteria: ECCS power peaking, shutdown =argin, and potential ejected rod worth. As discussed above, cc=pliance -ith the ICCS power peaking criterion i is ensured by the rod position limits. The da' - >vailable red worth, consistent with the rod position limits, provides for achieving act shutdown by reactor trip at any time, assuring the highest worth control rod that is withdrawn remains in the full out position (1). S e rod position limits also j ensure that inserted rod groups vill not contain single rod worths greater j than: 0.655 Ak/k at rated power. These values have been shown to be safe by the safety analysis (2) of the hypothetical red ejection accident. A maximum j single inserted control rod worth of 1.05 Ak/k is allowed by the rod position li=its at hot zero power. A single inserted control red verth 1.05Ak/k at beginning of life, hot, zero pcVer vculd result in a lower transient peak themal power and, therefore, less severe env-ionmental consequences than i 0.655 Ak/k ejected rod worth at rated power. 4 The plant computer vill scan for tilt and imbalance and vill satisfy the j technical specification requirements. If +he computer is out of service, than j manual calculation for tilt above 15 percent power and imbalance above h0 percent power must be perforced at least every two hours until the computer is i returned to service. I t i The quadrant power tilt limits set forth in Specification 3.5.2.h have been established within the thermal analysis design base using an actual core tilt of +h.925 which is equivalent to a +h.015 tilt reasured with the full incore l instrumentation with measurement uncertainties included. I During the physics testing program, the high flux trip setpoints are admini-stratively set as follows to assure an additional safety margin is provided: Test Power Trip Setroint 1 h3 505 50 505 75 355 >75 105.55 3-36

REFERE: ICES (1) FSAR, Secticn 3.2.2.1.2 l (2) FSAE, Section lb.2.2.2 1565 295 3-36a

P03ER LEVEL 100 138.102 274.1.102 CUT 0FF = 925 90 NOT ALLOWED 274.l 92 RESTRICTED g SHUT 00EN MARGIN LIMIT j 70 200,70 W 0 20,60 O 50 85,50 E 40 PERMISSIBLE 30 20 3,8.5 10 40,10 0,0 e i i i i e i i i i 0 25 50 75 100 125 150 175 200 225 230 275 300 Rod Index, % withdrawn 0 25 50 la 100 i f f i Group 7 Cn 0 25 50 75 100 i e i i i m R00 POSITION LIMITS FOR 4 PUMP g 100, W 6 0 2} 50 75 OPERATION FROM 0 TO TO 125 1 5 EFPD Group 5 TMI-1, CYCLE 4 Figure 3.5-2A g

E POIER 230 102 274.1.102 ' LEVEL ~ 100 idH ALLO 1ED S ,f _1 274.1.92 90 RESTRICTED 80 248.2,80 70 7 ~ 4 200,70 E N N 60 PERMISSIBLE O t., 50 168,50 f 40 30 20 118,15 120,10 10 0,2.7 t i I f I l 1 l l I l 0 25 50 75 100 125 150 175 200 225 250 215 300 Rod index, % withdrawn 0 25 50 75 100 ~ i i i i m G Group 7 u 0 25 50 75 100 t l t i N 0 25 50 50 7,5 100 Group 6 R00 POSITION LIMITS FOR 4 PUNP OPERATION T FROM 12515 EFP0 TO 265115 EFPD N Group 5 TMI-I, CYCLE 4 Figure 3.5-28

I 8 102 150,102 248.2.102 100 ICT ALLOWED RESTRICTED FOR 90 00,89 80 o SHUT 00fN MARGlN I 0,75 _E 70 LIMIT } 60 E 4 PERMI SSI BL E = 50 85,50 S Y E 40 A 30 N 10 4 'I 0,8.5 60,15 10 o,0 s 0 25 50 75 100 125 150 175 200 225 250 275 300 Rod Inden 5 witndrawn 0 25 50 75 100 i e i e i ~ Group 7 0 2p 50 7} Iq0 0 25 50 75 100 Group 6 P 2 & 3 PHP N OPERATION FROM 0 TO 12515 EFPO ' "E Tul-1, CYCLE 4 CO Figure 3.5-2C

230.102 248 2.102 100 90 5 80 NOT ALL0ff0 g 2 SHUTOOWN MARGIN 2 10 Lluli g c S h ~ 50 168,50 y PERulS$1BLE 40 JD 20 118.15 130.15 'O ~ 0, 2.1 i i f a t I i i I I 0 25 50 75 100 125 150 175 200 225 250 275 300 Rod indes, 5 Withdrann 0 25 50 75 100 i i Group 7 0 25 50 75 100 m i e i a Group 6 LJ1 0 25 50 75 100 R00 POSill0N LlutiS FOR 2 & 3 PUMP N Group 5 OPERATION FROM 125 ! $ TO 265 ! 15 EFPD g Tul-1, CYCLE 4 Figure 3.5-20

POWER, ',' OF 2535 MWt RESTRICTED REGION 110 -30.80,102' -- 100 -30.21,92 -- 90 -38.25,80 - 60 i 13.45,80 -- 70 PERMISSIBLE OPERATING REGION -- 60 -- 50 -- 40 -- 30 - 20 10 t i 1 i f l 1 I l 1 -50 30 -20 10 0 10 20 30 40 50 Axial Power imoalance, 5 1565 300 POWER IMBALANCE ENVELOPE FOR OPERATION FROM 0 TO 125 t 5 EFPD TMl-1, CYCLE 4 Figure 3.5-2E

POWER, 5 0F 2535 MWt RESTRICTED REGION - 110 -30.07,102 12.87,102 -29.14,92 90 13.45,92 -36.81,80 - 80 13.45,80 -- 70 PERMISSIBLE 60 OPERATING ~ REGION -- 50 - 40 30 i -- 20 -- 10 t I i I I I I l -50 -40 -30 -20 -10 0 10 20 30 40 50 Axial Power Imualance, 5 1565 301 POWER IMBALANCE ENVELOPE FOR OPERATION FROM 125 1 5 TO 265 1 15 EFP0 TMI-1, CYCLE 4 Figure 3.5-2F

21 20 Ig 5 I i 18 \\ = b 17 / / -N 3 / N / ~ 15 4 14 g 5 j 13 12 0 2 4 6 8 10 12 Axial location of Peak Power From Bottom of Core. It LOCA 1.lMITED MAXIMUM ALLOWABLE LINEAR HEAT RATE - TMI-1, CYCLE 4 Figure 3.5-2G 1565 302

57.9.102 100 RESTRICTED 90 57.9,80 80 g 70 100,70 = NN 60 PERMISSIBLE 50 REGION E 40 30 20 10 f f I f f f I I f 0 10 20 30 40 50 60 70 80 90 100 APSR ", witnarawn APSR POSITION LIMITS FOR OPERATION FROM 0 TO 265 1 15 EFP0 TMI-1. CYCLE 4 Figure 3.5-2H 1565 303}}