ML19312C534
| ML19312C534 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/17/1978 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19312C531 | List: |
| References | |
| NUDOCS 7912160092 | |
| Download: ML19312C534 (17) | |
Text
w
)
)
93 tsov lo, UNITED STATES
'g NUCLEAR REGULATORY COMMISSION y
,7 e
W ASHING TOP f. D. O. 20555 t
o s., -
/
DUKE POWER C0ttPANY DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT NO. 1 AMENDf4ENT TO FACILITY OPERATING LICENSE Anendment No. 59 License No. DPR-38 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duke Power Company (the licensee) dated January 23, 1978, complies 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 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, 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 requirements have been satisfied.
2.
Accordingly, the license is amended by a change to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 3.8 of Facility License No. DPR-38 is hereby amended to read as follows:
l "3.3 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Am.endment No. 59 are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications."
7912160 OfR
\\
s 2-3.
This license amendment is effective as of the date of issue 1cc.
FOR THE NUCLEAR REGULATi3Y COMMISSION jl' Y(.(< Cf N 's
}$',
,/
A. Sc ncer, Chief Ocerating Reactors Branch 41 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 17, 1978 l
l
UNITED STATES
[
NUCLEAR REGULATORY COMMISSION g
g WASHINGTON. D. C. 20555 4,..... Jf DUKE POWER *l0MPANY 1
t DOCKET N0. 50-247 OCONEE NUCLEAR STATION, UNIT NO. 2 AMENCt'ENT TO FACILITY OPERATING LICENSE Amendrent No. 59 License No. OPR-47 4
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duke Pcwer Company (the licensee) dated January 23, 1978, 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 Cornission'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 acplicable requirements have been satisfied.
2.
Accordingly, the license is amended by a change to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility License No. CPR-47 is hereby amended to read as follows:
"3.S Technical Specifications The Technical Specifications contained in Appendiccs A and B, as revised through Amendment No. 59, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications."
9 9
--r--
s 2-3.
This license amendment is effective as of the date of issuance.
FOR THE N'JCLEAR REGULATORY COMMISSION ffRffrid" f A.' Schwencer, Chief Operating Reactors Branch fl Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: Februa ry 17, 1978 P
O
D
?
i J
f **%q#o UNITED STATES
/
E' NUCLE AR REGULATORY COMMISSION i
g
]
3, f
WASHINGTON. D. C 20555
%,.....J DUKE POWER COMPANY DOCKET NO. 50-287 1
OCONEE NUCLEAR STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE 1
l Amendment No. 56 License No. DPR-55 4
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duke Power Company, (the licensee) dated January 23, 1978, 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; j
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 issuarce of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements nave been satisfied.
?.
Accordingly, the license is amended by a change to the Technical Spec-ifications as indicated in the attachment to this license anendment and t
paragraph 3.8 of Facility License No. DPR-55 is hereby amended to read j
as follows:
"3.3 echnical Scecifications l!
he Technical Specifications contained in Appendices A and B, as revised through Amendment No. 56, are nereby incorporated in the~ license.
The licensee shall caerate the facility in accordance with the Technical Specifications."
l l
I J
m -
m w,-
-t c - > -
r v-
<,w+.-
,w r
- - - - - ~
,.u-r-4 2
4 J
i, 2-l a
I 3.
This license amendment is effective as of the date of issuance, s
FOR THE NU EAR REGULATORY COMMISSION
!)hil W W O w A. Schwencer, Chief l
j Operating Reactors Branch #1 l
Division of Operating Reactors
Attachment:
t Changes to the Technical l
Specifications j
Date of Issuance:
February 17, 1978 J
I i
i J
l I
j I
t J
4
. ~. - _ -.
{ -
)
l l
ATTACHMENT TO LICENSE AMENDMENTS l,
AMENDMENT NO. 59 TO DPR-38 AMENDMENT'NO. 59 TO DPR-47 AMENDMENT N0. 56 TO DPR-55 1
DOCKET NOS. 50-269, 50-270 AND 50-287 i
j Remove the following pages and insert revised identically numbered pages:
3.5-7
)
3.5-8 3.5-9 3.5-10 t
3.5-11 3.5-13 3.5-18a i
3.5-21 3.5-23d 3.5-23e j
1 Delete the following pages:
3.5-13a 1
i
- 3. 5-18b i
3.5-21a 3.5-21b l
4 i
f i
i l
l l
i l
l
g.
If withis eno
- 4. hour of'do:=m -m:1cn of as
.cperable red, j
d it is no: do:::21:ed :ha c 1%ik/t hot si=2:devn margin exis:a j
J combining da verth, of the inoperablo :cd #..h eacs. of da other cds, the reac:c: shall be brough: :o da het sca=dby c ndi:1cu until "hd*
arg1= is established.
Toucving de determina:1:n of an i=cperable =d, all :=ds shall h.
be exar:1 sed d.hin 24 hcurs and exarcised weekly until '.he : d problem is solved.
i.
If a cen:::1 : d is -le :sgulating er safa:7 =d g cups is declarad i=cpershle, ;cve: shall be reducei := 60 peres== cf the the==al pcver auevable for the ranc::: cools : pu=p ccm-bi=aticn.
j.
If a conm 1 ::d i=. de regula:ing or axial pcvar sha:1=g g::ups is declared i=cperable, operscies abcvs 60 percent of 2:sd power =sy cen-d- - A ded. ha : ds i= de g::up ars posi.1: ed such tha: de : d. da: was der', ed i=cperable is a1=:sised vi-%d, allevabla g: cup average ;cs
-d ~-
-d 3 of SFe"'#' N :10 d
3.5.1.1.a.a i de viddrawal t' d:s of 5;er'#d-stica,3.3.2.3.c.
3.5.2.3
.The - r.hs ci singla. inser:ad. c:n-- '
- ds during :.:1-d "' ' 7 a:a 11=1:ed by.the res::1c.1 =s of seecifica ':n 1.1 21 a=d da.
'I cen::ci : i ;csi:1cu. Limi:s daf1=ed i= Scecifica:1:n 3.5.2.5.
3.5.2..a Quad..ss: ?cvar Til:
Excepe for physics ces:s, if da -n d a posi:ive. quad:sn ;c.er I
a.
cil:.ex:seds 3.41% Unit 1, ei:her :he quad s== pcwer :il shall l
3.11% Uni: I 3.41% Uni: 3 i
be reduced :o less chan 3.41% Uni: 1 vi his eno hours or tha l
T.4I: Uni: 2 3.41 Uni 3 following acticus shall be :aken:
(1) If four : sac:or ecolan: pumps are i=. operatica, de allevable 9 = "* 1 power shall be reduced belcw da ;cver level en:off (as, identified is specift:scica 3.5.2.5) and further reduced 1.
l l
by 2% of full power for each.1 :11: is excess of 3.41% Usi:
3_ /.1; Uni:- 1 3.41 Uni: 3 (2) If less : ban. four reactor coolanc pumos are is operatien, de alicwabis :hermal pcver for de reac::r coola== pump c=rio1=a:1cs
.shan be reduced by 2% of d ?cver for each 1 til:.
3.5-7 l
Antndment Nos. 59, 59 & 56
s (3)
Execpt as pr vid:d in specificaticn 3.5.2.4.b, tha rcactor shall be brought to the hot shutdown condition within four hours if the quadrant power tilt is not reduced to less than 6.03% Unit I within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.41% Unit 2 3.41% Unit 3 b.
If the quadrant tilt exceeds 3.41% Unit I and there is simultaneous 3.41% Unit 2 3.41% Unit 3 indication of a misaligned control rod per Specification 3.5.2.2, reactor operation may continue provided power is reduced to 60%
of the thermal power allowable for the reactor coolant pump combination.
c.
Except for physics test, if quadrant tilt exceeds 9.44% Unit 1, 9.44% Unit 2 9.44% Unit 3 a controlled shutdown shall be initiated immediately, and the reactor shall be brought to the hot shutdown condition within four hours.
d.
Whenever the reactor is brought to hot shutdown pursuant to 3 5 2.4.a(3) or 3.5.2.4.c above, subsequent reactor operation is permitted for the purpose of measurement, testing, and corrective action provided the thermal power and the power range high flux setpoint allowable for the reactor coolant pump combination are restricted by a reduction of 2 percent of full power for each I percent tilt for the maximum tilt observed prior to shutdown.
Quadrant power tilt shall be monitored on a minimum frequency e.
of once every two hours during power operation above 15 percent of rated power.
3.5.2.5 Control Rod Positions a.
Technical Specification 3.1.3 5 does not prohibit the exercising of individual safety rods as required by Table 4.1-2 or apply to inoperable safety rod limits in Technical Specification 3.5.2.2.
b.
Except for physics tests, operating rod group overlap shall be 25% + 5% between two sequential groups.
If this limit is exceeded, corrective measures shall be taken immediately to achieve an accep-table overlap. Acceptable overlap shall be attained within two hours or the reactor shall be placed in a hot shutdown condition within an additional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Position limits are specified for regulating and axial power c.
shaping control rods. Except for physics tests or exercising control rods, the regulating control rod insertion / withdrawal i
I limits are specified on figures 3.5.2-1A1 and 3.5.2-1A2 (Un'it 1); 3 5.2-181, 3.5.2-182 and 3.5.2-1B3 (Unit 2);
3 5.2-Ici, 3 5.2-Ic2 and 3.5.2-Ic3 (Unit 3) for four pume operation, and on figures 3.5.2-2Al and 3.5.2-2A2 l
(Unit 1); 3 5 3-2B1, 3.5.2-2B2 and 3.5.2-2B3 (Unit 2);
3 5.2-2ci, 3 5.2-2c2 and 3.5.2-2c3 (Unit 3) for two or three 3.5-8 Amendmeq* Nns. 59, 59 & 56
pumpoperstit)Also,cxceptingphysicst0sts
- cxarcising centrol rods, th] cxiol power sh ping control rad insarticn/
withdrawal lialts aro specificd cn figuros 3.5.2-4Al, and 3.5.2-4A2 (Unit 1); 3 5.2-481, 3.5.2-4B2, and.3 s5.2-4a3 (Uni t 2),
l and 3.5.2-4C1, 3.5.2-iC2, and 3.5.2-4C3 (Unit 3).
If the control rod position limits are exceeded, corrective measures shall be taken imediately to achieve an acceptable control rod position.
An acceptable control rod position shall than be attained within two hours.
The minimum shutdown margin required by Specification 3.5.2.1 shall be maintained at all times.
i d.
Except for physics tests, power shall not be Increased above the power level cutoff as shown on Figures 3.5 2-1 Al, and 3.5.2-1 A2 (Uni t 1), 3.5.2-1B1, 3.5.2-182, and 3.5.2-183 (Uni t 2), and 3.5.2-Ici, 3.5.2-Ic2, 3.5.2-Ic3 (Unit 3), unless the following requirements are met.
(1)
The xenon reactivity shall be within 10 percent of the value for operation at steady-state rated power.
(2)
The xenon reactivity worth has passed its final maximum or minimum peak during its approach to its equilibrium valve for operation at the power level cutoff.
3.5.2.6 Reactor power imbalance shall be monitored on a frequency not to exceed two hours during power operation above 40 percent rated power.
Except for physics tests, imbalance shall be maintained within the envelope defined by Figures 3.5.2-3A1, 3.5.2-3B1, 3 5 2-382, 3.5 2-3S3, l
3.5 2-3ci, 3 5 2-3c2, and 3.5.2-3C3 If the imbalance is not within the envelope defined by these figures, corrective measures shall be taken to achieve an acceptable imbalance, if an acceptable imbalance is not achieved within two hours, reactor power shall be reduced until imbalance limits are met.
3.5.2.7 The control rod drive patch panels shall be locked at all times with limited access to be authorized by the manager or his designated alternate.
3.5-9 Amendment Nos. 59, 59 & 56
Ba s s Th2 power-imbalanca cnvalepa d3 fin:d in Figurcs 3 5.2-3A1, l
3.5.2-381, 3.5.2-382, 3.5.2-353, 3.5.2-3C1, 3.5.2-3C2 and 3 5 2-3C3 is based on LOCA analyses which have defined the maximum linear heat rate (see Figure 3.5.2-5) such that the maximum clad temperature will not exceed the Final Acceptance Criteria. Corrective measures will be taken immediately should the Indicated quadrant tilt, rod position, or Imbalance be outside their specified boundary. Operation in a situation that would cause the Final Acceptance Criteria to be approached should a LOCA occur is highly improbable because all of the power distribution parameters (quadrant tilt, rod position, and imbalance) must be at their limits while simultaneously all other engineering and uncertainty factors are also at their limits.**
Conservatism is introduced by application of:
a.
Nuclear uncertainty factors b.
Thermal calibration c.
Fuel densification power spike factors (Units 1 and 2 only) d.
Hot rod manufacturing tolerance factors e.
Fuel rod bowing power spike factors The 25% + 5% overlap between successive control rod groups !s allowed since the worth of a rod is lower at the upper and lower part of the stroke.
Control rods are arranged in groups or banks defined as follows:
Group Function 1
Safety 2
Safety 3
Sa fe ty 4
Sa fe ty 5
Regulating 6
Regulating 7
APSR (axial power shaping bank)
The rod position 1i nits are based on the most 1Imiting of the foilowing three criteria:
ECCS power peaking, shutdown margin, and potential ejected rod worth.
Therefore, compliance with the ECCS power peaking eriterion is ensured by the rod position limits. The minimum available rod worth, consistent with the rod position limits, provides for achieving hot shutdown by reactor trip at any time, assuming the highest worth control rod that is withdrawn remains in the full out position (1).
The rod position limits also ensure that inserted rod groups will not contain single rod worths greater than 0.65%
ak/k at rated power. These values have been shown to be safe by the safety analysis (2,3,4,5) of hypothetical rod ejection accident.
A maximum single inserted control rod worth of I.0%ak/k is allowed by the red position limits at hot zero power. A single inserted control rod worth of 1.0% ak/k at beginning-of-life, hot zero power would result in a lower transient peak thermal power and, therefore, less severe environnental consequences than a
0.65% ak/k ejected rod worth at rated power.
- Actual operating limits deoend on whether or not incore or excore detectors are used and their respective instrument calibration errors.
The method used to define the operating lhits is defined in plant operating procedures.
3.5-10 Amendment Nos. 59, 59 & 56
~
/
Centrol rod groups aro withdrawn in s;qu:nca b: ginning with Group I.
Groups 5, 6, and 7 are cvaricpp:d 25 parcsnt.
Th2 normal positten at power is for Groups 6 and 7 to be partially inserted.
The quadrant power tilt limits set forth in Specification 3 5.2.4 have been established to prevent the linear heat rate peaking increase associated with a positive quadrant power tilt during normal power operation from exceeding 5.10% for Uni t 1.
The limits shown in Specification 3.5.2.4 I
5.10% for Unit 2 5.10% for Unit 3 are measurement system independent.
The actual operating limits, with the appropriate allowance for observability and instrumentation errors, for each measurement system are defined in the station operating procedures.
The quadrant tilt and axial imbalance monitoring in Specification 3 5.2.4 and 3 5.2.6, respectively, normally will be performed in the process computer.
The two-hour frequency for monitoring these quantities will provide adequate surveillance when the computer is out of service.
Allowance is provided for withdrawal limits and reactor power imbalance limits to be exceeded for a period of two hours without specification violation. Acceptable rod positions and imbalance must be achieved within the two-hour time period or aopropriate action such as a reduction of power taken.
Operating restrictions are included in Technical Specification 3 5.2.5d to prevent excessive power peaking by transient xenon.
The xenon reactivity must be beyond its final maximum or minimum peak and approaching its equili-brium value at the power level cutoff.
REFERENCES FSAR, Section 3 2.2.1.2 FSAR, Section 14.2.2.2 3 FSAR, SUPPLEMENT 9 4
B&W FUEL DENSlFICATION REPORT BAW-1409 (UNIT I)
BAW-1396 (UNIT 2)
BAW-1400 (UNIT 3) 50conee 1, Cycle 4 - Reload Report - BAW-1447, March 1977, Section 7.11 3.5-11 l
i Amendment Nos. 59, 59 & 56
J (174,102) g (153,102)
J
'(300,102)
OPERATION IN THIS RESlON (274,90) 90
/ POWER uiNiuuu g gg3,, o )
80 SHUTOOWN LEVEL h
LlulT CUTOFF 2
70 OPE R ATION IN THIS REGION 18 RESTRICTEO (256,60) 60 8
(150,50) 50 g
E 40 5'
PERulSSIBLE 30 OPE RATIN G REGION 20 -
(110,15) 10
( 64,0) 0 00 14 0 ISO 220 260 300 ROD INDEX,'/o WITHDRAWN OCONEE 1 CYCLE 4 RCD POSITION LIMITS FOR FOUR PUMP OPERATION AFTER 100 + 10 EFPD a\\ OCONEE NUCLEAR STATION Figure 3.5.2-1A2 3.5-13 Amendrrent Nos'. 59, 59 & c
~
)
E h 100
$2,102) g go OPERATION IN THIS REGION o
13 NOT ALLOWED WITH s Pump 2 OR 3 PMS 80 mest cre (252,80) s IN TNf 3 assoM g
v a:
e 9 S
j I
(172, 50 )
va
{ 40 d
4 30 PERMISSIBLE o
OPERATING g to REGION (110,15 )
g 10 E
o 0 60 10 0 14 0 ISO 220 260 300 ROD INDEX,*/, WITHDRAWN OCONEE 1 CYCLE 4 R0D POSITIO" LIMITS FOR TWO AND THREE PUMD OPERATION AFTER 100 10 EFFD
\\ OCONEE NUCLEAR STATION Figure 3.5.2-2A2 3.5-18a Amendment Nos. 59. 59 & 56
~
POWER. 5 of 2568 Nft RESTRICTED REGION 110 (9.0.102)
( 17.3.102) 100 (8 8.90)
( 15.3.90) 90 80 70 PERNISSISLE OPERATING 60 RANGE 50 40 30 20 10 l
l O
i 1
-20 10 0
+10
+20 Core Imoalance. *,
OPE:TIONAL POWER IMBAla' ICE ENVELOPE, Unit 1
.itheil OCONEE NUCLEAR STATION 3.5-21 Figure 3.5.2-3Al Amendment Nos. 59, 59 & 56
(11.0,102)
(32.0,102)
RESTRICTED 100 REGION 90 (8.6.90)
>(34.4,90) l.(6.2,80) o (34.4.80) 80 (6.1,70)
<d34.4,70) 70 (85.4.60) 60 w (6.1,60) m (0.60)
(100,60) 50 PERMISSIBLE h
40 OPERATING f
REGION 30 20 10 0
I I
I I
I i
i l
I l
0 10 20 30 40 50 60 70 80 90 100 APSR. $ Witnarawn APSR POSITION LIMITS FOR OPERATION AFTER too (:10)
EFPD, UNIT 1 b\\
put em s, OCONEE NUCLEAR STATION W
Figure 3.5.2-4A 2
- 3. 5-23d Amendment Nos. 59, 59 & 56
s I
i Entire Page Deleted 3.5-23e Amendmer.t Nos. 59, 59 & 56 I
l