ML20092F216
| ML20092F216 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 06/12/1984 |
| From: | Rivenbark G Office of Nuclear Reactor Regulation |
| To: | Cleveland Electric Illuminating Co, Toledo Edison Co |
| Shared Package | |
| ML20092F219 | List: |
| References | |
| NPF-03-A-069 NUDOCS 8406230314 | |
| Download: ML20092F216 (33) | |
Text
. - -
o UNITED STATES g
f g
NUCLEAR REGULATORY COMMISSION 3:
qj WASHINGTON, D. C. 20555 Y
,o THE TOLED0 EDIS0N COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET N0. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 69 License No. NPF-3 i
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by The Toledo Edison Company)and The Cleveland Electric Illuminating Company (the licensees dated February 17, 1984, as revised March 29, 1984, ccmplies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 regulations of the Comission; 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 ccaducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, Facility Operating License No. NPF-3 is hereby amended as indicated below and by changes to the Technical Specifications as indicated in the attachment to this license amendment:
Revise paragraph 2.C.(2) to read as.follows:
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l 2-Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 69 are hereby incorporated in the license. The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION cst '/ :6 b**tb n
George W. Rivenbark, Acting Chief Operating Reactors Branch No. 4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 12, 1984 r
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ATTACHMENT TO LICENSE AMENDMENT NO. 69 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 Replace the following' pages of the Appendix."A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
Pages 3/4 1-26 3/4 1-28b 3/4 1-28c 3/4'l-28d 3/4 1-29b 3/4 1-29c 3/4 1-29d 3/4 1-34 3/4 1-37 3/4 1-38 3/4 1-39 3/4 1-40 3/4 1-41 3/4 1-42 3/4.1-43 3/4 2-1 3/4 2-2b 3/4 2-2c 3/4 2-2d
'3/4 2-3b 3/4.2.3c
<3/4 2-3d 3/4 2-12
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i REACTIVITY CONTROL SYSTEMS SAFETY R0D INSERTION LIMIT LIMITING CONDITION FOR OPERATION 3.1.3.5 All safety rods shall be fully withdrawn.
APPLICABILITY:
1* and 2*f.
ACTION:
With a maximum of one safety rod not fully withdrawn, except for surveillance testing pursuant to Specification 4.1.3.1.2, within one hour either:
a.
Fully withdraw the rod or b.
Declare the rod to be inoperable and apply Specification 3.1.3.1.
)
SURVEILLANCE _ REQUIREMENTS 4.1.3.5 Each safety rod shall be determined to be fttily withdrawn:
Within 15 minutes prior to withdrawal of any. regulating a.
rod during an approach to reactor criticality.
6.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter..
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- See Special Test Exception 3.10.1 and 3.10.2.,
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3c REACTIVITY CONTROL SYSTEMS REGULATING ROD INSERTION LIMITS
' LIMITING CONDITION FOR OPERATION 3.1.3.6 The regulating rod groups shall be limited in physical insertion as shown on Figures 3.1-2a, -2b. and -2c and 3.1-3a, -3b, and -3c for the first 200 210 EFPD of operation. If the axial power shaping rods are completely withdrawn at 200 10 EFPD for extension of cycle length, then the regulating rod groups shall be limited in physical insertion as shown on Figures 3.1-2e and 3.1-3e for the remainder of the cycle.
However, if the axial power shap-ing rods are not completely withdrawn at 200 210 EFPD, then the regulating rod groups shall be Ifmited in physical insertion as shown'on Figures 3.1-2d and 3.1-3d for the remainder of the cycle. A rod group overlap of 25 :5%
shall be maintained between sequential withdrawn groups 5, 6 and 7.
APPLICABILITY: MODES 1* and 2*#.
ACTION:
With tne regulating rod groups inserted beyond the abov~e insertion limits (in a region other than acceptable operation), or with any group sequence or over-lap outside the 'specified limits, except for surveillance testing pursuant to Specification 4.1.3.1.2, either:
f a.
Restore the regulating groups to within the limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or b.
Reduce THERMAL POWER to less than or. equal to that fraction of RATED THER-MAL POWER which is allowed by the rod group position using the above fig-ures within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or i
- c.
Be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
NOTE:
If in unacceptable region, also see Section 3/4.1.1.1.
'See Soecial Test Exceptions 3.10.1 and 3.10.2.
sWith k,ff-2 1.0.
l OAVIS-BESSE, UNIT 1 3/4'l-26.
Amendment No. 77, JJ,'07, f7,=.
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REACTIVITY CONTROL SYSTEMS o00 pe0gaAM LIMITING CON 0! TION FOR Op! RATION 3.1.3.7 Each control rod (safety, regulating and APSR) shall be pro-grassied to operate in the core position and rod group specified in I
Figure 3.1-4.
APPt.ICA8!!.!TY: MODES l' and 2*.
ACTION:
4 With any control rod not programmed to operate as specified above, be in i
HOT STAN08Y within I hour.
SURVE!LLANCE REQUIREMENTS 4.1.3.7 a.
Each control rod shall be demonstrated to be programed to operata in the specified core position and rod group by:
1.
Selection and actuation from the control room and veriff-cation of movement of the procer rod as indicated by both t.ie absolute and relative position incicators:
a)
For all control rods, after the control rod drive patches are locked subsequent to test, reprograming or maintenanca within the panels, b)
For specifically affected individual rods, following maintenance, test, reconnection or modification of l
power or instrumentation canles from the control rod l
i drive control system to the control rod drive.
2.
Verifying that each cable that has been disconnected has been properly metened and reconnectea to tne specified control rod drive, b.
At least once eacn 7 days, verify that the control rod drive paten panels are locked.
'see special Test Exceptions 3.10.1 and 3.10.2.
DAVIS-SESSE, UNIT 1 3/4 1-30 Ameneent No.11 l-l
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1 REACTIVITY CONTROL SYSTEMS XENON REACTIVITY l
LIMITING CONDITION FOR OPERATION 3.1.3.8 THERMAL POWER shall not be increased above the power level cutoff specified in Figure 3.12 unless one of the following conditions is satisfied:
a.
Xenon react.ivity is witnin 10 percent of the equilibrium i
value for RATED THERMAL POWER and is approaching stability, or b.
THERMAL POWER has been within a range of 87 to 92 percent of RAND THERMAL POWER for a period exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in the soluole poison control mode, excluding xenon free start-ups.
r AP9LICASILITY: MCD; 1.
ACTION:
With the recuirements of the above specification not satisfied, recuca THERMAL POWER to less enan or equal to the power level cu.cff witnin 15 minutes.
~
SURVE*LLANCE REQUIREM DTS 4.1.3.3 Xenon reactivity shall be determined to be within 10% of the equilibrium value for RATED THERMAL PCWER and to be approaching stability or it snall be detennined that the THERMAL POWER has been in :ne range :f 37 to 925 of RATED THERMAL POWER for 3 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />,. prior to increasing IHERMAL POWER above the power level cu, toff.
'f DAVIS-8 ESSE, UNIT.1
_3/4 1-33 i
i
REACTIVITY CONTROL SYSTEMS AXIAL POWER SHAPING ROD INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1.3.9 The axial power shaping rod group shall be limited in physical in-sertion as shown on Figures 3.1-Sa, -Sb, -Sc, -Sf, -5g and -Sh for the first
- 200 210 EFPD of operation.
If this rod group is completely withdrawn at 200 210 EFPD for extension of cycle length, it shall not be reinserted in the core for remainder of the cycle and the limits of Figure 3.1-5e shall be aco'icable.
However, if the rod group. is not completely withdrawn at 200 :10 EF:0, tne group shall be limited in physical insertion as shown on Figures 3.1-5d and
-51 for the remainder of the cycle.
APPLICABILITY: MODES I and 2*.
ACTION:
With the axial power shaping rod group outside the above insertion limits, i
l either:
1 Restore the axial power shaping rod group to within the limits within 2 a.
hours, or b.
Reduce THERMAL POWER to less than or equal to that fraction of RATED l
THERMAL POWER which is allowed by the rod group position using the above figures within 2 nours,pr c.
De in at least HOT STAND 3Y within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.3.9 The cosition of the axial power shaping rod grouc shall be deter-mined to be within the insertion limits at least once every 12 nours except when the axial power shaping rod insertion limit alarm is inoperable, then verify the group to be within the insertion limit at least once every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
With k,ff a 1.0.
DAVIS-BES3E, UNIT 1 3/4 1-34 Amendment No. U, f2, M, 67, 69 i
Figure 3.1-5c.
APSR Position Limits, 150 10 to 200 = 10 EFPD, Four RC Pumps - Davis-Besse 1, Cycle 4 (8,102)
(38,l'02) 100 C
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(38,92)
RESTRICTED REGION 2
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10 20 50 60 70 80 90 100 APSRPosition(f. Withdrawn)
DAVIS-BESSE, UNIT 1 3/4 1-37 Amendment No. 33, g, $1,69
Figure 3.1-5d. APSR Position Limits, 200 10 to 240 : 10 I'
EFPD, Four RC Pumps - Davis-Besse 1, Cycle 4 (8, l'02)
(38,iO2) 100 C
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(38,92)
E 80 (
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a RESTRICTED REGION I
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60 e
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(iOO,50) e W
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10 20 3
4 50 60 70 80 90 100 APSA Position (f. Withdrawn) l DAVIS-BESSE, UNIT l 3/4 1-38 Amendment No. JJ, pg, AE, 57.69
Figure 3.1-Se. APSR Position Limits, 200 10 to 280 : 10 EFPD, Three or Four RC Pumps, APSRs Withdrawn --
Davis-Besse 1, Cycle 4 110 l
100 l
90
- ?
80 C2 70 APSR INSERil0N NOT ALLOWED
=
IN THIS TIME INTERVAL 55 60 S
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40 2
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20 10 0
O 10 20 30 40 50.
60 70 Su 90 100 APSR Position (5 #itnarawn)
DAVIS-BESSE, UNIT 1 3/4 1-39 Amendment No. 72, 45, 57, 69 l
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Figure 3.1-5f.
APSR Position Limits, O to 24+10/-0 EFPD, I
Three RC Pumps - Davis-Besse 1, Cycle 4 120 l
50 0 g
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(38.77)
U (8. 69. 5)
(38,69.5) w 60( (0.60.5)
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RESTRICTED REGION I
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40 PERMISSIBLE S
OPERATING REGION (iOO.38) 5-!
A 20 1
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10 20 30 40 50 60 70 80 90 100 APSR Posi tion (", Wi tacrawn) i DAVIS-BESSE, UtlIT I 3/4 1-40 Amendment flo. #, $1, 69
Figure 3.1-5g.
APSR Position Limits, 24+10/-0 to 150 10 EFPD, Three RC Pumos - Davis-Besse 1, Cycle 4 120 g iOO W2
-(8.77)
(38.77) 80 RESTRICTED (8.69.5)
(38.s9.5)
REGION e*
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- ( 42,60. 5) g 60C t
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PERMISSIBLE (100*38) g OPERATING REGION 2
20 0
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f f
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0 10 20 30 50 60 70 30 90 100 APSR Posi tion (T. Wi tharawn) l DAVIS-BESSE, UNIT 1 3/4 1-41 Amendment No. A), 57,69
Figure 3.1-Sh. APSR Position Limits, 150 10 to 200 : 10 EFPD, Three RC Pumps - Davis-Besse 1, Cycle 4 120 E iOO W
i 2
a 80
- (8.77)
(38.M RESTRICTED REGION 5
(8.69.5)
(38.69.5) m U$
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40 PERMISS!BLE OPERATING REGION 20 0
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10 20 30 40 50 60 70 80 90 100 APSR Position (#. Wi tharawn)
I l
l l
DAVIS-BESSE, UNIT 1 3/4 1.42 Amendment No. 6, 6,69
Figure 3.1-5f.
APSR Fosition Limits, 200 10 to 240 : 10 EFPD, Three RC Pumps - Davis-Eesse 1, Cycle 4 120
)
2 iC0 W2
- (8,77)
(38,77)
RESTRICTED REGION 80 Et r
g (8,69.5)
(38,69.5) s 60 <
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PERMISSI Bl.E (100,38)
CPERATING REGION 20 0
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10 20 30 4
50 60 70 80 90 100 APSRPosition(f.Witadrawn)
DAVIS-BESSE, UNIT 1 3/4 1-43 Amendment No. 95, 57, 69
1 3/4.2. POWER OISTRIBUTION LIMITS AXIAL POWER IMBALANCE.
LIMITING CONDITION FOR OPERATION 3.2.1 AXIAL PmdER IMBALANCE shall be maintained within the Ifmits shown on Figures 3.2-la, -lb and -Ic and 3.2-2a -2b and -2c for the first 200 zio i
EFPD of operation.
If the axial po.wer shaping rods are completely withdrawn at 200 10 EFP0 for extension of cycle length, then the AXIAL POWER IMBALANCE shall be maintained within the limits shown on Figares 3.2-le and 3.2-2e for the remainder of the cycle. However, if the axial power shaping rods are not completely withdrawn at 200 =10 EFPD, then the AXIAL POWER IMBALANCE shall be maintained within the limits shown on Figures 3.2-id and 3.2-2d for the re-mainder of the cycle.
APPLICA8ILITY: MODE 1 above 40% of RATED THEPNAL POWER.*
ACTION:
.With AXIAL POWER IMBALANCE exceeding thu limits specified above, either:
a.
Restore the AXIAL POWER IMBALANCE to within its limits within 15 minutes, or 1
b.
Within one hour reduce power until imbalance limits are met or to 40" of RATED THERMAL POWER or less.
f SURVEILLANCE REOUIREMENTS I
4.2.1.
The AXIAL POWER IMBALANCE shall be determined to be within limits at-l least once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when above 40% of RATED THERMAL POWER except when the AXIAL POWER IMSALANCE alarm is inoperable, then calculate the AXIAL POWER j
IMBALANCE at least once per hour.
i 4
i
- 5ee Soectal Test Exception 3.10.1.
i DAY!S-BESSE, UNIT'I' 3/4 2-1 Amendment No. JJ. ii. #5 fl. 69 i
Figure 3.2-la.
Axial Power Imbalance Limit;, O to 24+10 -0 EFPD, Four RC Pumps - Davis,Besse 1, Cycie 4
(-17,iO2)
(20,IO2)
- 100
(-22,92)
(25,92)
- 90
(-25,80)
{-- 80 (30,80) 8 c.
g-- 70 i;
- 60 PERMISSISLE OPERATING Q
RESTRICTED REGION 8
REGION t--
50 t
8g--w 2:..
b 30 g-m.
20 iO I
I I
I I
-30
-20
-10 0
10 20 30 Axial Power imealance (f.)
DAVIS-BESSE, UtlIT 1 3/4 2-2 Amendment flo. JJ, JtJI, g,61
Figure 3.2-lb.
Axial Power Imbalance Limits, 24 + 10
-0 to 150 + 10 EFPD, Four RC Pumps - Davis-Besse 1, Cycle 4
( 20, iO2)
(-21,102)
- 100
(-26,92)
(25,92) 90
(-29,80) g 80 (30,80) u2 70 a
h PERMISSIBLE w
OPERATING A
60 RESTRICTED REGION REGION a:
50 "a
@y n
s.
30 g
20
- 10 i
l i
I i
-30
-20
-10 0
10 20 30 AxialPowerImbalance(",)
I i
DAVIS-BESSE, UflIT 1 3/4 2-2a Ame;,dnent flo. 77, 7), M, h$,61
. s ee J
Figure 3.2-lc. Axial Power Imbalance,150 10 to 200 10 EFPD, Four RC Pumps - Davis-Besse 1, Cycle 4
(-26,102)
(20,l'02)
- 100
(-31,92)
- 90 (25,92)
(-38,80) 80
( 30,80)
_5 E
a
~ 70 a
f RESTRICTED PERNISSIBLE E-60 REGION OPERATING S
i REGION j
,-- 50 o
cg-w g- - 30 E
20 l
l'0 1
I I
I I
I
-4
-30
-20
-10 0
10 20 30 AxialPowerlabalance(f.)
l l
l l
DAVIS-BESSE, UNIT 1 3/4 2-2b Amendment No. O, M,,Q,69 l
Figure 3.2-ld.
Axial Power Imbalance Limits, 200 : 10 to 240 : 10 EFPD, Four RC Pumps - Davis-Besse 1, Cycle 4
(-26,iO2)
(20,l'02)
- 100
(-31,92)
(25,92) 90
(-38,80)
- 80 (30,80) 2 W2 70 g
TRICTED PERNISSI 8LE A
60 REGION
~
o OPERATING REGION f-- 50 a
48-40 bS j- - 30 E
20 io I
I I
I I
I
-30
-20
-10 0
l'c 20 30 AxialPowerlabalance(f.)
DAVIS-BESSE, UNIT 1 3/4 2-2c Amendment No. f), 57,69
\\
Figure 3.2-le.
Axial Power Imbalance Limits, 200 : 10 to 280 e 10 EFPD, Four RC Pumps, APSRs Withdrawn -
Davis-Besse 1, Cycle 4
(-22,102)
(23,102)
- 100
(-30,92)
(30,92)
_9
(-35.80) 80 25 o'
- 70 w
iE 60 PERMI SSI BLE O
OPERATlNG REGION E
- 50 p
O RESTRICTED 3
_ go REGION I
j
- 30 I
e l
l
- 20 10 l
f I
I I
I I
I
-30
-20
-10 0
10 20 30 l
Axial Power imoalance (7,)
i I
i f
DAVIS-BESSE, UNIT 1 3/4 2 2d Amendment No. (), 77,$9 i
O
~
Figure 3.2-2c.
Axial Power Imbalance Limits, 150 10 to 200 2 10 EFPD, Three RC Pumos - Davis-Besse 1 Cycle 4
- - 100
- 80 (i5.77)
(-23.25.69.5)
(i8.75.69.5) 2
(-28.5.60.5)
W-- 60 (22.5.60.5) 2 a
5 g--%
tE cr o
PERMISSI BLE g
OPERATING
=
REGION g-20 RESTRICTED m-REGION 5
3 c.
l l
t t
I l
-30
-20
-10 0
10 20 30 Axial Power imbalance (5) i i
DAVIS-BESSE, UNIT I 3/42-3b
/ Amendment No. JZ, JJ, $7, 6!
Figure 3.2-2d.
Axial Power Imbalance Limits, 200 10 to 240 10 EFPD, Three RC Pumps - Davis-Besse 1. Cycle 4
- - 100
- a0 (i5,n) g _,,,,, y)
(-23.25,69.5)
(i8.75,69.5) 2
(-28.5,60.5)
- 60 (22.5,60.5) 1 S--#
CE ac o
P ERMIS$18LE OPERATING E
REGION g-20 RESTRICTED a:.
REGION t
i.
a.
l l
1 t
f I
l l
-30
-20 i0 0
i0 '
20 30 i
Axial Power labalance (f.)
l l
DAVIS-BESSE, UNIT 1 3/4 2-3c Amendment No. AJ, $1,69
- - ~ - - - -. -. -. -. -.., - -
.~
Figure 3.2-2e.
Axial Power Imbalance Limits, 200 10 to 280 : 10 EFPD, Three RC Pumps, APSRs Withdrawn - Davis-Besse 1, Cycle 4 100 I
~~
(-16.5.77)
I
(-22.5.69.5)
(22.5.69.5) l 5
e
(- 26. 25.60. 5) 5-60 m.
d I
4 O
40 y-as 3
RESTRICTED PERMI SSI BLE REGION OPERATING g
REGION gg-20 y
l 3
l l
l I
i f
f 1
- 30
-20
-10 0
10 20 30 l
Axial Power imoalance (5) l DAVIS-BESSE, UNIT 1 3/4 2-3d Amendment No. AJ, $7, 69
, I',.
i
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POWER DISTRIBUTION LIMIT 5
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g i
L1MIT!NG CON 0! TION FOR OPERATION (Continued)
ACTION:
(Continued) s d.
With the QUADRANT POWER TILT detemined to exceed the Maximus Limit of Table 3.2-2. TWuce THERMAL POWER to 1 15t of RATED -
THDMAL POWER within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.-
t,
\\
2RVEILLANCE REQUIREMENTS
\\
f 1
4.2. 4 The QUADRANT POWER TILT shall bi Jetemined to be within the limitt at least once every 7 days durim caeration above 15% of RATED
~. ' s.e TriERMAL POWER except when the QUACRANT fCWR TILT alam is inocerable, then the QUADRANT POWER TILT shall be calestated at least once per 12 1
hours. '
r
,).
s
- , s s
(
! 'i,'7-y t
e e
,(
\\*
s
.\\(
s s,
n
'I r
DAVIS-8 ESSE, UNIT 1 3/4 2-11 s
<y' l r
('
t i
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Table 3.2-2 Quadrant Power Tilt Limits (Tech. Soec. Table 3.2.2) 1 t
[l' Steady state Transient Maximum limit limit limit Measurement independent 4.92 11.07 20.0 QUADRANT POWER TILT QUADRANT POWER TILT as measured by:
Symmetrical incore 3.43 8.93 20.0 detector system Power range channels 1.96 6.96 20.0 Minimum incore detector system
- 1. 90 4.40 20.0 4,
f,
)
L, lt b
?
4
- l,'
i i
i l
3/4 DAVIS-BESSE, UNIT 1 Amendment No. 77, 33, /E, 69
.-