ML19282B911
| ML19282B911 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 02/16/1979 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19282B907 | List: |
| References | |
| NUDOCS 7903190020 | |
| Download: ML19282B911 (19) | |
Text
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UNITED STATES 3 %,..
4;' t NUCLEAR REGULATORY COMMisslON Mj$
{,. (j{541 '1/p/
WASHINGTON, D. C. 20$55 o, 4 gv, COMMONWEALTH EDISON COMPANY DOCKET NO. 50-295 ZION STATION UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE
~
Amendment No. 42 License No. _DPR-39 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonweal th Edison Company (the licensee) dated February 2,1979, as supplemented February 9,1979, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; 6.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable require-ments have been satisfied.
I9031900.2e
1 I
a
! i 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility License No. DPR-39 is hereby amended to read as follows:
(2) Technical Specifications i
The Technical. Specifications contained in Appendi.es A and B, as revised through Amendment No. 42, are hereby incorporated in the license.
The licensee shall operate the facility in accordance wi+.h the j
Technical Specifications.
3.
This license amendment supercedes the Order for Modification of License dated April 21, 1978 and is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
, 4s dw e
A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating 'leactors
Attachment:
Changes to the Technical Specifications Date of Issuance: February 16, 1979 l
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,8 UNITED STATES y'U.
- ' g NUCLEAR REGULATORY COMMISSION C,
WASHINGTON, D. C. 20555 g,, g 4 '
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COMMONWEALTH EDISON COMPANY DOCKET N0. 50-304 ZION STATION UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 39 License No. DPR-48 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated February 2,1979, as supplemented February 9,1979, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. _ The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable require-nents have been satisfied.
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility License No. DPR-48 is hereby amended to read as follows:
(2) Technical Speqifications The Technical Specifications contained in Appendices
~
A and B, as revised thro';gh Amendment No. 39, a re hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amer.dment supct cedes the Order for Modification of License dated April 21, 1978 and is effective as of the.date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION f
./
gjwen A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: February 16, 1979 G
ATTACHP1ENT TO LICENSE AMENDMENTS AMENDMENT NO. 42 TO FACILITY OPERATING LICENSE NO. DPR-39 AMENDMENT NO. 39 TO FACILITY OPERATING LICENSE NO. DPR-48 DOCKET NOS. 50-295 AND 50-304 Revise Appendix A as follows:
Remove pages 45, 45a, 46, 47, 47a, 63a, 67, 68a and 69a and replace with the attached identically marked revised pages identified by the above amendment numbers.
Revisions are noted in the margin of the pages by a vertical line.
Insert attached new pages 46a, 46b, 69b and 69c, also identified by amendment number.
b O
LIMIT] NG CONDITION FOR OPERATION SURVP.ILLANCE REQUIRIGIENT 3.2.2 Power Distribution Limits 4.2.2 Power Distribution A.
Ilot Channel Factor Limits
- A.
Hot Channel Factor Limits 1.1 At all times, except during physics 1.1 Following initial core loading tests at $$75% rated power **, the and at a minimum of regular hot channel factors defined in th effective full power monthly bases must meet the follcwing limits:
intervals thereafter, power distribution maps, using the Units 1 and 2 movable detector system, shall be made to confirm that the hot
~
Q(Z) 1.86/P x Kl(Z), for P3>.5 O(Z)4 P
F
=-
channel factor limits of this L 3.72 x K1(Z), for P f.5 s ecification are satisfied 41.55 1+0. 2 (1-P) X RDP, and l'hil~
Following initial loading and each subsequent reloading, a where:
power distribution map using the Movable Detector System, Fg(Z)
=F9(Z) limit; shall be made to confirm that L
power distribution limits are p' constant (LOCA limiting value))
met, in the full power con-1.86 = F figuration before a unit is P= fraction of rated poser at which operated above 75% of rating.
andFjH the core operated during FQ measurement]
factor from Figure 3.2-9 selected K (Z) a at the core elevation, Z, of the measured Fg;
- The hot channel factors above are defined for a period not to exceed the predicted minimum time to collapse exposure levels for each fuel region as referenced in the bases.
- During physics tests which may exceed these hot channel factor limits, the reactor may be in his condition for a period of time not to exceed eight hours continuously. /Wendment No. 42, Unit 1 Amendment No. 39, Unit 2
LIMIT 3NG CONDITION FOR OPERATION SURVEILLANCE REQUIRDIE1IT 3.2.2.A.l.1 (RodBowPenalty)=(1-IfH Penalty),
RBP andFyg Penalty is obtained from Figure 3.2-6 as a function of fuel region average burnup in MWD /MTU.
The raeasurement of total peaking factor, P lica s, shall ha increased by g
three: [.ercent to account for 2..:inuL.cturing tolerancas and further increased by five percent to account for raeasurement error.
The neasurement of enthalpy rise hot cha:uiel factor, F[I shall ba increased H,
by four percent to account for measure-ment errors.
1.2 If the measured hot char:nel factors exceed the limits in Item 3.2.2.A.l.1 of this specification, the reactor power and the high neutron flux trip setpoints shall be reduced in direct proportion to the excess over the peaking factor which is limiting for that unit.
- 45a -
Amendment No. 42, Unit 1 Amendment ho. 39, Unit 2
LI!!1 'lo i:G COliDITION FOR Ol'BRATICI:
GU!tW.ILLANCE REQUIRIF.Si:T
.i. 2. 2. A. f. 2 (Con
- t) 4.2.2.A.1.2 if subsequent i.n-core mapping cannot, 2.1.a vithin a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period, demonstrate that the hot channel factor limits This APDMS type surveillance is are mot, the reactor shall be brought conducted with at least.two incore to the hot shutdown condition with return thimbles at the following frequency:
to power authorized only for the purpose of physi.cs testing.
(1) At least once per 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, if above PT*
(2) Immediately and every two hours IL the turn-on power fraction, P for ten hours following the tha,n (defined in the bases) is less events listed below:
1.00, then APDMS type surveillance must beconductedtomeet[Pset 3(z) the APDMS (a) Raising the power, if above t.ype surveillance point, (de f ined 12,.
in the bases) while the power is above PT, e xce pt-when surveillance is being dono for liASE LOAD operation (Section (b) Moving the control bank of 3. 2. 2. A. 2. 2.).
rods more than an accumulated total of 5 steps in any one 2.3.b direction, if above P,p.
.I C the conditions of Section 2.1.b 3.2.2.A.2.1.a cannot be mot, then immediately take action (and reduce Conduct APDMS type surveillance with necessarytoensureh-](z) power) as at least two incore thimbles in met or reduce power to below immediately after taking action to P I'.
re-establish P.(z)<
F (n) 3 3
s I Amendment No. 42, Unit 1 Amendment No. 39, Unit 2
9 q.t.
.m a rou pm.
LIMITIllG CONDITION FOR OPER ATION SURVEILLANCE REQUIREMENT
'II.2.2.A.
3 2.2.A.
2.2.a 2.2.a y
The maximum allowed power for BASE Not Applicable.
TDAD operation is the lenser of:
- 1. Rated t,hermal pcw
- o
- 2. Power limited by g(Z The nominal minimum power for BAkk LOAD operation is the lescer c C:
- 1. Maximum allowed pcuer less 5%
cf rated thermal pi wer, or
- 2. Pcwer limited by APDMS type surveillance.
BASE IDAD operation can replace operation innder APDMS type surveillance only if section 3.2.2.u.2.2.b l a satis fied.
2.2.b 2.2.b Prior to going to BASE IDAD cperation After waiting the 218 hours0.00252 days <br />0.0606 hours <br />3.604497e-4 weeks <br />8.2949e-5 months <br />, ana-und prior to discontinuing APDMS type sur-lyze a full core flux map near the veillance (Section 3.2.2. A.2.1), maintain pcwer level that is limited by APDMS the follcuing conditions for 216 hours0.0025 days <br />0.06 hours <br />3.571429e-4 weeks <br />8.2188e-5 months <br />; type surveillance. Prior to going above the power level limited by APDMS
- 1) Power must be maintained near the type surveillance, dete-mine from this power limited by APDMS type sur-fluxmapthepowerlimitedby{F(Z}
Q veillance.
for BASE IBAD operation.
- 2) 6I within a +3% AI tarcct band.
If the conditions of L ?ction For BASE LOAD operation, the follow-3.2.2.A.2.2.b. are satisfied, then BASE T/MD ing surveillance requirements shall operation may replace operaticn under APDMS apply:
t,ype surveillance provided the following is (1) at less than cr equal to the power maintained:
level that was determined to be limited by Fq(Z8 L for DASE LOAD operation, o tain a full core flux map at least one week, two weeks and monthly af ter achievinc a BASE IDAD mode of operation.
Amendment No. 42, Unit 1 d
Amendment No. 39, Unit 2
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREHE!?P 3.2.2.A 4.2.2.A 2.2.c (Continued) 2.2.c.
(1) Power between the maximum and (2)
A flux difference alarm shall indicate non-conformance with minimum limits specified in the 13% AI target band for 3.2.2.A.2.2.a.
BASE LOAD operation. If the (2) AI within the AI target band alarm in temporarily out of as per section 3.2.2.A.4 and service, conformance with the 3.2.2. A.5, except une +3% AI applicable limit and the flux target band instead of the +6, difference shall be logged
-7% AI target band.
hourly for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and half-hourly thereafter.
2.2.d If any of the requirements of Section 2.2.d Not Applicable 3 2.2.A.2.2.c. are not maintained then power must immediately be reduced to below the power limited by APDMS type surveillance (section 3.2.2.A.2.1.) and APDMS type surveillance must be ini-t1ated if the power la above Ey.
3.2.2.A.3 4.2.2. A.3 The target flux difference at a given The reference equilibrium indicated power level, Po, to determined by noting axial flux difference as a function of the indicated axial flux difference at the power level (called the target flux power level with equilibrium xenon condi-difference) shall be determined at least tions established in the core, part once per equivalent full power quarter.
length rods fully withdrawn, and with the The target difference should be updated full length rod bank more than 190 stepa every effective full power month. This withdrawn.
Po for the purpcse of deter-may be done using the measured value for mining the target value, should be as that month or by linear extrapolation high a power level as practicable.
The using the two most recent measured va-target flux difference at any other level, lues.
The initial target flux difference on a reload may be determined from design P, is equal to the target value of PO multiplied by the ratio, P/P.
predictions.
O Amendment flo. 42, Unit 1 Amendment tio. 39, Unit 2
SURVEILLANCE REQUIREMENT LIMITING COMDITION FOR OPERATION 4.2.2.A 3 2.2.A.4 4.
Except during physics tests, during 4.
Not applicabic encore calibration procedures and czcept aa modified by Items 5 through 7, the indicated axial flux difference shall be maintained within +6, -7% of the target flux l
difference (this defines the 61 target band on axial flux differ-ence).
5 At a pouer level greater than 90 5
A flux difference alarm shall indicate non-l percent of P,
l conformance with the AI target band around the T
target valae for operation at power levein 5.1 If the indicated axial flux l
above 90% of P.
If the alarm la temporarily T
out of service, conformance with the applica-difference deviates from its ble limit and the flux difference shall be target band, either the devia-tion shall be eliminated or the logged hourly for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and reactor power shall be imme-half-hourly thereafter.
diately reduced to a level no l
greater than 90 percent of PT and Item 6 applies.
6.
At a power level no greater than 90 6.
A flux difference alarm shall indicate non-conformance with the limit on time (one hour
{
percent of P,
penalty time in 24) that the 6I target T
6.1 The indicated axial flux band may be exceeded for operation at or be-If this alarm in temporarily difference may deviate from its lou 90% of PT.
out of service, conformance with the applica-l LLI target band for a maximum ble limit and the flux difference shall be penalty time of 1 hr (cumula-logged hourly for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and half-tive) in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period provided the flux difference hourly thereafter.
does not exceed an envelope Amendment No. 42, Unit 1 Amendment No. 39, Unit 2
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.2.2.A.6 bounded by + Y percent and - 3 percent 4.2.2.A at a power of 90% of P and increa-T sing by +1 percent and -1 percent for each 2 percent of rated power below 90% of P.
Where if = 10.8% of PT T
rounded down to the nearest percent.
6.2 If item 6.1 is violated then the reactor power shall be redaced to no greater than 50% power and the high neutron flux setpoint reduced to no greater than 55% of rated values.
7.
At a power level no greater than 50 per-7.
Not applicable.
cent of rated power.
7.1 The indicated axial flux difference may deviate from its target band.
7.2 A power increase to a level greater than 50 percent of rated power is contingent upon the indicated axial flux difference not being outside its target band for more than one hour (cumulative) out of the pre-ceding 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.
Amendment No. 42, Unit 1 Amendment No. 39, Unit 2
-47A-
Figure 3.2-9 Hot Channel Factor Normalized Operating Envelope for Units 1 and 2 F
Cenatant (LOCA Limiting Value) = 1.86 q
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Amendment No. 42, Unit 1 Amendment No. 39, Unit 2
- 63a -
g(Z), lle ight Dependent IIcat Flux Ilot Channel ItshouldbenotedthatFfH, F
is based on Factor, is defined as the maximum local heat integral and is used as such in the DNB flux on the uurface of a fuel rod at core calculations.
Local heat fluxes are obtained elevation Z divided by the average fuel rod by using hot channel and adjacent channel heat flux, allowing for manufacturing explicit power shapes which take into account tolerances on fuel pellets and rods.
variations in horizontal (x-y) power shapes throughout the core.
Thus, the horizontal g
F9, Nuclear Heat Flux Ilot Channel Factor, is power shape at the point of maximum heat flux isnotnecessarilydirectlyrelatedtoPyg, defined as the maxin.um local fuel rod linear power density divided by the average fuel rod linear power density, assuming nominal fuel An upper bound envelope, F9(Z) limit, has been pellet and rod dimensions, determined from extensive analyses considering all operating maneuvers consistent with the y
Ph,EngineeringHeatFluxHotChannelFactor, technical specifications on power distribution in defined as the allowance on heat flux re-control as given in Section 3.2.2.
The results cuired for manufacturing tolerances.
The of the loss of coolant accident analyses based engineering factor allows for local variations on this upper bound envelope indicates the peak 0
in enrichment, pellet denalty and diameter, clad temperature will not exceed the 2200 F surface arca of the fuel rod and eccentricity limit.
The Fg (Z) limit includes the higher upper of the gap between pellet and clad.
Combined head temperature considerations (12).
statistically, the net effect is a factor of 1 03 to be applied to fuel rod surface heat flux.
Pfg, Nuclear Enthalpy Rise Hot Channel Factor, is defined ao the ratio of the integral of linear power along the rod with the highest integrated power to the average rod power.
Amendment No. 42, Unit 1 Amendment No. 39, Unit 2,
The procedures for axial power distribution The alarms provided are derived from the plant, control referred to above are designed to minimize process computer which determined the one the ef fecta of xenon redistribution on the axial minute averages of the operable excore detector power distribution during loadfollow maneuvers.
outputs to monitor twI in the reactor core and Easically control of flux difference is required alerts, the operator when AI alarm conditions to limit the difference between the current value exist.
Two types of alarm messages are output, of Plux Difference (.esI) and a reference value Above a preset pcwer level, an alarm which corresponds to the full power equilibrium message is output immediately upon determining value of Axial offset ( Axial Offset = 6I/ fractional a delta flux exceeding a preset band about a pouer).
The reference value of flux difference target delta flux value.
Eelcw thia preuet varies uith power level and burnup but expressed power level, an alarm message is output if the as axia] offset it varies only with burnup.
6 I exceeded its allowable limits for a prepet cumulative amount of time in the past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The technical cpecifications on power distribution For periods during which the alarm on flux lcontrolanurethat the FQ 11ait is not exceeded and difference is insparacle, manual auenil3ance
> crain ula t.d/Ricns are nct developed which at a uill be utilized to provide adequata mpning of iator tira, would cause greater local power peaking sigiaificant variations in expected flux even though the flux difference is then within the dif rerence s.
However every attempt should be limits specified by the procedure, made to restore the alarm to an cperable condition as soon as possible.
An deviations The target (or reference) value of flux difference from the target band during manual logging shall is deter.nined au follows.
At any time that be treated as deviationa during the entire equilibrium xenon conditions have been established, preceeding logging interval and appropriate the indicated flux difference is noted with part actions shall be taken.
This action is necessary length roda withdrawn from the core and with the to satisfy NRC requirements; however more fu)) Jongth rod control rod bank more than 190 frequent readings may be legged to minimize the steps withdrawn (i.e. normal full power operating penalty associated with a deviation from the position appropriate for the time in life, target band to justify continued operation usually withdrawn farther as burnup proceeds).
at the current power.
This value, divided by the fraction of full power at which the core was operating is the full power The times that deviations from the band occur value of the target flux difference.
Values for are normally accumulated by the computer.
all other core power levels are obtained by multiplying the fell power value by the fractional power.
Since the indicated equilibrium value was noted, no allowances for excore detector of the esI target band are permitted from the indicated reference value.
During periods where extensive
/W:endment No. 42, Unit i load following is required, it may be impractical lbiendment No. 39, Unit 2 to establish the required core conditions for measuring target flux difference every month.
For this reason, the specification provides two methods for updating the target flux difference.
-68a-
significantly different from those resulting For Condition II events the core is protected from operation within the target band.
The from overpower and a minimum DNER of 1.30 by instantaneous consequences of being outside the an automatic protection system.
Compliance band, provjded rod insertion limits are observed, with operating procedures is assumed an a is not worse than a 10 percent increment in precondition for Condition II transients, peaking factor for flux difference in the range however, operator error and equipment mal-f(Y +3f percent (4 Y percent to - Y percent in-functions are separately assumed to lead to dicated) increasing by +1 percent for each 2 the cause of the transients considered.
percent decraase in rated porter. Therefore, while the deviation exists the power level is limited lfluxdifference.T or lower depending on the indicated to 90% of P If, for any reason, flux difference is not con-ltrolledwithinthe A I target band for as long a period as one hour, then xenon distributions may be significantly c danged and operation at 50 per-cent is required to protect against potentially more severe consequences of some accidents.
As discussed above, the essence of the procedure is to maintain the xenon distribution in the core an close to the equilibrium full power condition as possible.
This is accomplished, without part length rods, by using the boron system to position the full length control rods to produce the re-quired indicated flux difference.
It is accom-pliched, when part length control rods anc used, by using the boron system to position the full in a desired range and length ccr' O
u.;e part length bank to con-L 1.. t m.x:g. e.
The difference between thenc tuo tethodt is in the rate at which a return to full power can be accomplished uhen there is an increase in plant pcuer demand.
Amendment No. 42, Unit 1 Amendment No. 39, Unit 2
-69a-
Above the TURN-ON power fraction, PT, additional c.
E 1
R j=
13 axial power distribution monitoring system type n
1:1 (APDMS type) surveillance is required except during Base Load Cr,eration.
APDMS type surveillance in-E, for thimble j, is determined from volvea measurement of normalized axial power dis-a least n-6 incore flux maps repre-tributions, F Z), for thimble j using movable sentative of the full range of the AI incore instrula;(zntation.
Tnic surveillance involves target Band Operations.
Most recent encuring or taking actiorl to ensure that Fj(Z) is flux maps will be used to update RJ 1enn t,han, it: ye tpcint, (Fj(Z]
3, so that either by making n> 6 or by replacing
[F(Z)]L.
By limiting the core average the old flux maps with the recent maps, F (Z) $
Q Q
axial power dintribution the total power peaking factor Fo(Z) can ba limited since all other com-meas ponents remain relatively fixed.
The remaining pQ i Rj=
(3 i
part of the total power peaking factor can be derived based on incore measurements i.e. an ef fective radial. peaking factor, R, can be deter-and F j(Z) is the normalized axial mined as the ratio of the total peaking factor i
results from a full core flux map and the axial distribution at elevation Z from peaking factor in a selected thimble, thimble j in map i which had a measured peaking factor without uncertainties f Fmeas.
Equations, definitions, and Explanations:
Q1 1
g
~
7 (Fo(Zh EI
- ~
1"1
( j-Ri j ) ",
3 ) (1 + or ) (1. 3)(1.07) 3=
~
J j
E d
IfAPD(MSeuipmentisusedforthissurveillance, will be further reduced by 1.5% to then Pj(Z c
is standard deviation of R3 and is account for equipment round off errors.
1 dePived from n flux maps or 0.C2, which-ever is greater.
The main criteria for b.
PT = Turn-On power fraction selecting thimbles to be used in APDMS type surveillance will be based on Fq constant (LOCA limiting value) selecting those with the smallestDj.
maximum Fq constant from 4-loop design The value of G~j will also be used as a guide to evaluate when older flux map predictions of swing-and-base load operation data is no longer adequate.
1.03=F[j e.
f.'
l.07 is the sum of two factors, 5% measurement uncertainty associated with the use of the incore flux measurement system and 2% additional Amendment No. 42, Unit 1 Amendment No. 31 Unit 2 conservatism for APDMS type sur-veillance technique.
-69b-
Bases:
Base load operation involves restricting operation to a narrow range of power distributions to en-that Po (z)f[Fo (z)]
This sure vi11 be verified by fub'1 core flux r.e, <urveillances at th intervals inen'.;itied in Sectior e.2.2.A.2.2.
The power level at which
[Fg (z)] g will be reached will be d6termined in a conservative man.ier from full core flux maps taken at lower powers.
Also, oper-ation near the power level at which
[Pg (z)]
first occurs will be just-iried b,y full core flux maps.
d Amendment No. 42, Unit 1 Amendment No. 39, Unit ?
LIMITIllG COlIDITIO!I FOR OPERATI0li SURVEILLANCE REQUIREMENT 3.8 5,
Accumulator System 4.8 5.
Accumulator System (Table 4.8-4)
A.
The four accumulator systems shall satisfy the following conditions A.
Surveillance and testing of the whenever the reactor coolant system accumulator system shall be pressure exceeds 1000 psig except performed as follows:
as specified in 3.8.5.A.5.
1.
Each accumulator shall be 1.
The pressure and level of the pressurized to at least 600 accumulator tanks shall be poig and ghall contain minimum checked once a shift. At each of 770 ft3 and a maximum of 5% increase in level, the 818 ft3 of water.
boron concentration will be checked.
2 Each accumulator shall contain 2.
The accumulator boron concen-water borated to at least tration shall be checked 2000 ppm.
monthly.
3.
Each accumulator's isolation 3.
The accumulator check valve valve shall be open, operability (SI-8948A, B, C,
and D and SI-8956A, B, C,and D) will be verified at each refueling outage by opening the accumulator outlet isola-tion valve (MOV-SI8808A, B, C,
and D) and verifying a de-crease in accumulator level and by a leakage test to de-termine that no gross valve leakage is experienced.
4.
Isolation Valves Not Applicable.
Amendment No. 42, Unit 1 Amendment No. 39, Unit 2
-174-
.