ML20248D889
| ML20248D889 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/28/1998 |
| From: | Capra R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20248D893 | List: |
| References | |
| NFP-73-A-092, NFP-73-A-92, NUDOCS 9806030124 | |
| Download: ML20248D889 (16) | |
Text
- _ - - _ _ _ _ - _ - _ - - _ - _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - -
Mro p
'h UNITED STATES s
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 3000H001 DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMSAh[Y DOCKET NO. 50-334 BEAVER vat i FY POWER STATION. UNIT NO.1
. AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.215 License No. DPR-66 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duquesne Light Company, et al. (the licensee) dated March 16,1998, as supplemented May 14,1998, 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 (1) 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 epplicable requirements have been satisfied.
l i
9806030124 980528 f
PDR ADOCK 05000334 P
PDR l
2-2.
A.sa4;,, gly, the license is amended by changes to the Technical SperJeGons as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-66 is hereby amended to read as follows:
(2) TetnicalSpecifications The Technical Sperr,c Gons contained in Appendix A, as revised through Amendment No.215, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance, to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION l
pe&
Robert A. Capra, Director Project Directorate I-2 Division of Reactor Projects - 1/ll Office of Nuclear Reactor Regulation Atttdiment: Changes to the Technical Specifications Date of issuance: May 28, 1998 l
l
s.
ATTACHMENT TO LICENSE AMENDMENT NO. 215 FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Replace the following pages of Appendix A Technical Specifications, with the enclosed pages as indicated. The revised pages are identified by amendment number and contain verticallines indicating the areas of change.
Remova Inand 3/4 3-11 3/4 3-11 3/4 3-12a 3/4 3-12s B 3/4 3-ic
{
l
}
h 6
ce 6
ic hnd R
Wae
)
4 4 I
P lr 1
1 D
nli
(
(
5 iiu 3
4 ea sve
,5 2
2 2
f 3
2 2 2 2 2 err I
S du A.
,d I
T oS n
E N
N N
1 2 1 1
14 2a 1 1 1 1 1 E
M E
R I
U O
l E
a R
ln eot E
ni s C
I I
I
)
nteI I
I 1
W.
acTI I
I
(
(
0 I
L hn U1 U
U L
Cu
{
/
/
F SR Q
S Q g
S 3Q Q Q Q Q Q IEVRUS n
1 o
N li
)
3 O
et 3
( I I
na 4
T nr I
A ab
,Q E
T hi L
N Cl A.
)
)
)
)
I
)
)
2 d6 6 6
6 6
6 B
E a
n(
(
I
(
I
(
(
A N
C N Da R R R
R R
R R R R R T
URTS N
I l
ek N
nc E
ne T
ah A.
A.
A.
A.
S hC Y
C N
S S N N
S N
S S S S S S
x P
I x
x x
u h
R u
u u
l wg T
l l
l F
oi F
F F
L H R
n O
n n
n o
e e T
p o
o o
r r r C
i r
re re e t
T u u A
r t
tt tt g u
A s s r t
E T
u ua ua n e
s s e n
t R
t e
eR eR a N
e e e t i
n i r N
N N
R r
r r a o
i n o e
e u
P P W p
o
,v
,v ex e) t T U t
,t p
c e
ei ei t u g0 al r r r e
t
/
l a g
gt gt al n1 r e e eh S
e a e n
ni n a iF a-e r z z zg n R a
S as agd RP p e i i ii hg wRo Re en m w r r rH o
R P
N mo ew e o u u u-il i
o t a r
r r
rr cot p s s sl H
L c u e
eh eh et rl r r s s se n n w
wg wg tu ue e e e e ev oi oi ne oB v v r r re u a o
F N P a b PH PH IN S( O O P P PL
. 0 1 1
2 3
4 5
6 7 8 9 1 1
h 6
ce 6
ic hnd R
waeI
) I 4
44 P
lr1 1I D
nli I I iiu 3 3S ea sve err f 2
f I
S du I
T oS E
N M
1 11111 14 E
M ER IUOE t
la R
ln eot E
nis C
nte'
, I N
I acT
) I I
A hn 3
1I U 23 I
I Cu I
( I
/
L F
M RRRRR MRS
)
I d
E e
V u
R n
U i
S t
no n
N li o
O et C
I na
(
T nr A
ab 1
T hi N
cl A.
) ) ) I A.
6668 3
E a
( ( ( I M
C N RRRRR N
4 UR E
T L
S B
N A
I l
T ek M
nc E
ne A.
A. A. A. A. A.
A.
T ah S
hc Y
C N
NNNNN N
S P
T i
m s
C g
e s
A o
t a
E L
s p
R t
y y
i p S
B ni U r p
p T
i i
l rs r
a c Tk T
n i c
03 s
o t r o 6 8 911 rr i a ol - - - - -
oe t m tr PPPPP tk c o ce ca n t at ae er u u en F A RI ABCDE RB 2
3 4
2 2
2
[
i DPR-66 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES fESFi INSTRUMENTATION (Continued) l The instrumentation functions that receive input from neutron detectors are modified by a note stating that neutron detectors are excluded from the CHANNEL CALIBRATION.
The CHAhliEL CALIBRATION for the power range neutron detectors consists of a normalization of the detectors based on a power calorimetric and flux map performed above 154 RATED THERMAL POWER.
The power range neutron detector CHANNEL CALIBRATION is performed every 18 months but is not required for entry into MODE 2 or 1 en unit startup because the unit must be in at least MODE 1 to perform the test.
The neutron detector CHANNEL CALIBRATION for the source range and intermediate range detectors consists of obtaining detector characteristics and performing an engineering evaluation of those characteristics.
The intermediate range neutron detector CHANNEL CALIBRATION is performed every 18 months but is not required for entry into MODE 2 on ' unit startup because the unit must be in at least MODE 2 to perform the test.
The source range neutron detector CHANNEL CALIBRATION is performed every 18 months but is not required for entry into MODE 2 or 3 on unit shutdown because the unit must be in at least MODE 3 to perform the test.
The P-6 permissive neutron detector CHANNEL CALIBRATION is performed in conjunction with the intermediate range neutron i
detectors.
The overtemperature AT, P-8, P-9 and P-10 permissive neutron detector CHANNEL CALIBRATIONS are performed in conjunction with the power range neutron detectors.
l I
l BEAVER VALLEY - UNIT 1 B 3/4 3-ic Amendment No.215
s p
p t
UNITED STATES NUCLEAR REGULATORY COMMIS&lON "t
WASHINGTON, D.C. 30086-0001 DUQUESNE LIGHT COMPANY OHlO EDISON COMPANY THE CLEVELAND ELECTRIC l ILLUMINATING COMPANY THE TOLEDO EDISON COMPANY DOCKET NO. 50-412 BEAVER vat i FY POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 92 License No. NPF-73 1.
The Nuclear Regulatory Commission (the Commission) has fcund that:
A.
The application for amendment by Duquesne Light Company, et al. (the licensee) dated March 16,1998, as supplemented May 14,1998, complies with the standards 1
and requirements of the Atomic Energy Act of 1954, es 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, j
the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) 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 requirements have been satisfied.
i l
i 1
! l 2.
Accordingly, the license is amended by changes to the Technical Specifications as inoicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-73 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 92, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. OLCO shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance, to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION Robert A. Capra, Director Project Directorate 1-2 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuanca: May 28, 1998 I
l i
ATTACHMENT TO LICENSE AMENDMENT NO. 92 l
FACILITY OPERATING LICENSE NO. NPF-73 DOCKET NO. 50-412 Replace the following pages of Appendix A, Technical Specifications, with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicatine the areas of change.
Remove 103g1 X
X 3/4 3-10 3/4 3-10 3/4 3-12 3/4 3-12 B 3/4 5-4 B 3/4 3-4 8 3/4 3-5 8 3/4 3-5 B 3/4 3-6 B 3/4 3-6 B 3/4 3-7
NPY-73 INDEX BASES l
SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE (AFD)...................B 3/4 2-1 3/4.2.2 AND 3/4.2.3 HEAT FLUX AND NUCLEAR ENTHALPY HOT CHANNEL FACTORS Fg(Z) AND Fh............. B 3/4 2-2 3/4.2.4 QUADRANT POWER TILT RATIO...c.................B 3/4 2-5 3/4.2.5 DNB PARAMETERS.....'...........................B 3/4 2-5 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION...........B 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION........................B 3/4 3-1 3/4.3.3 MONITORING IN5iTRUMENTATION 3/4.3.3.1 Radiation Monitoring Instrumentation..........B 3/4 3-5 l
3/4.3.3.2 Movable Incore Detectors......................B 3/4 3-5 3/4.3.3.3 Seismic Instrumentation.......................B 3/4 3-5 3/4.3.3.4 Meteorological Instrumentation................B 3/4 3-6 l
3/4.3.3.5 Remote Shutdown Instrumentation...............B 3/4 3-6 l
3/4.3.3.7 Chlorine Detection Systems....................B 3/4 3-6 3/4.3.3.8 Accident Monitoring Instrumentation...........B 3/4 3-6 3/4.3.3.11 Explosive Gas Monitoring Instrumentation......B 3/4 3-7 l
3/4.3.4 TURBINE OVERSPEED PROTECTION..................B 3/4 3-7 l
3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION...................................B 3/4 4-1 3/4.4.2 AND 3/4.4.3 SAFETY VALVES.........................B 3/4 4-2 3/4.4.4 PRESSURIZER...................................B 3/4 4-2 BEAVER VALLEY - UNIT 2 X
Amenc ment No. 92 a
7 h
F ce P
ic N
hnd I
NaeI 4*
I lrI I
1 nli I
(
(
iiu 3 3 S 4 2
ea sve
,5 err 2
2 2
3 2 2 2 2 2
)
S du r
oS
,d 7
(
I n
n.
N 1
1 g 1 1
14 2a 1 1 1 1 1 r.
a B
R IU O
l E
la R
en not E
nis',
I
)
I
)
C ateI 1
I 1
N hcTI
(
I
(
A Cn g
g U
3 L
u j
/
L F
Q g Q Q
S 3Q Q Q Q Q Q I
EVRU n
S o
1 li
)
N et 3
( I 3
O na I
nr I
4 T
ab
,Q A
hi
)
)
)
)
3
)
I E
T Cl A.
2 d6 6 6
6 6
6 L
N a
n(
(
(
(
(
(
I B
E C N Da R R R
R R
R R R R R A
N T
URT l
S ek N
nc I
ne A.
A.
A.
ah N
hC E
C N
S S N N
S S
S S S S S TS YS h
n g
P o
x i
I x
x x
r u
h H R
u u
u t
l w
g -
T l
l l
u F
o i l F
F F
e L
H e R
N n
v O
n n
n o
e e e T
p o
o o
r r
r L C
i r
re re e t
T u
u S
r t
tt tt g u
A s
s r t
E T
u ua ua n e
s s e n
t R
t e
eR eR a N
e e
et i
n i r N
N N
R r
r r a o
i e
e n o p
o u
P P W v e e) t T
,v U t
,t p
c e
ei ei t g0 aA r) r r) e t
gt gt a n1 r e7 e e7 l
a gS e
a e n
ni nai a-e r z-z z-S n R a
as agd RP p e iP i iP h
o R
g w RoRe e m w r r r il P
N m ew e o ue u ue i
o t a r
r r
r cot p sv s sv H
L c u e
eh eh ex rl r r so s so n n w
wg wgtu ue e e eb e eb u a o
oi oi nl oB v v rA r rA F N P a b PH PH IF S( O O P( P P(
~0 1
1 2
3 4
5 G
7 8 9 1 1
7 h
F ce P
ic N
h n d ),
I Wae4 4
I lr1 4
1 I
nli
(
(
I iiu 3 3
5 ea sve err 2
2 2
I S
du 4
I T
oS N
N y
1 1
1 1
1 14 ENER IU O
l E
la R
en not E
nis C
ate N
hcT)
) I 23 A
Cn 5
1 I L
u
(
( I L
F M
R R
R R
R MR
)
I d
E e
V u
R n
U n
i S
o t
li n
N et A
O na I
nr T
ab t
A hi 3
I I
)
1 T
Cl A.
A.
8 6
8 N
a
(
I I
(
3 E
C N R
R R
R R
N N
4 U
R E
T l
L S
ek B_
N nc A
I T
ne ah A.
A.
A.
A.
A.
A.
A.
N hC E
C N
N N
N N
N N
TS Y
S s
r P
3 e
I 1
k R
a T
P e
e 0
r R
g6 8
9 1
B O
c n-e T
i m
aP P
P P
er s
C g
e R
su s
A o
t
, ls a
E L
s ex x
x x
us p
R t
y tu eu eu eu pe y
i p S al gl gl gl mr B
ni i F nF nF nF IP U r p
d a
a a
p T
i en Rn Rn Rn er i
l rs mo o
o o
ne r
a c Tk rr rr rr rr i b T
ni c
et et et et bm o t ro tu wu wu wu ra r
i a ol ne oe oe 6e uh o
t m tr IN PN PN PN TC t
c o ce c
n t at a
u u en e
F A RI A
B C
D E
R 2
3 4
2 2
2
NPF-73 3/4.3 INSTRUMENTATION I
BASES 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM AND ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continued) t Table 3.3-1 Action 2 has been, modified by two notes.
Note (4) allows placing the inoperable channel in the bypass condition for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> while performing:
a) routine surveillance testing of other channels, and b) setpoint adjustments of cther channels when required to.
reduce the setpoint in accordance with other technical specifications.
The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> time limit is justified in accordance with WCAP-10271-P-A, Supplement 2, Revision 1,
June 1990.
Note (5) only requires SR 4.2.4 to be performed if a Power Range High Neutron Flux channel input to QPTR becomes inoperable.
Failure of a component in the Power Range High Neutron Flux channel which renders the High Neutron Flux trip function inoperable may net effect the capability to monitor QPTR.
As such, determining QPTR using the movable incore detectors once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> may not be necessary.
The following discussion pertains to Table 3.3-3, Functional Units 6.b and 6.c and the associated ACTION 34.
The degraded voltage protection instrumentation system wil1 automatically initiate the separation of the offsite power sources from the emergency buses.
This action results in an automatic diesel generator start signal being generated as a direct result of the supply breakers opening between the normal and emergency buses.
The failure of the degraded voltage protection system results in a loss of one of the automatic start signals for the diesel generator.
Therefore, the ACTION statement requires the affected diesel generator to be declared inoperable if the required actions cannot be met within the specified time period.
The instrumentation functions that receive input from neutron detectors are modified by a note stating that neutron detectors are excluded from the CHANNEL CALIBRATION.
The CHANNEL CALIBRATION for the power range neutron detectors consists of a normalization of the detectors based on a power calorimetric and flux map performed above 15% RATED THERMAL POWER.
The power range neutron detector CHANNEL l
CALIBRATION is performed every 18 months but is not required for l
entry into MODE 2 or 1 on unit startup because the unit must be in at I
least MODE 1 to perform the test.
The neutron detector CHANNEL CALIBRATION for the source range and intermediate range detectors consists of obtaining detector characteristics and performing an engineering evaluation of those characteristics.
The intermediate range neutron detactor CHANNEL CALIBRATION is performed every 18 months but is not required for entry into MODE 2 on unit startup because the unit must be in at least MODE 2 to perform the test.
The source range. neutron detector CHANNEL CALIBRATION is performed every 18 months but is not required for entry into MODE 2 or 3 on unit BEAVER VALLEY - UNIT 2 B 3/4 3-4 Amendment No.92
....., ~.. _ _
l NPF-73 3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM AND ENGINEERPh SAFETY ff,ATURES AurUATION SYSTEM INSTRUMENTATION (Continuad) shutdown because the unit must be in at least MODE 3 to perform the test.
The P-6 permissive neutron detector CHANNEL CALIBRATION is performed in conjunction with the intermediate range neutron detectors.
The overtemperature AT, P-8, P-9 and P-10 permissive i
neutron detector CHANNEL CALIBRATIONS are performed in conjunction with the power range neutron detectors.
3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that:
- 1) the radiation levels are continually measured in the areas served by the individual' channels; 2) the alarm or automatic action is initiated when the radiation level trip setpoint is etxceeded; and
- 3) sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.
This capability is consistent with the recommendations of NUREG-0737,
" Clarification of TMI Action Plan Requirements," October, 1980.
3/4.3.3.2 MOVABLE INCORE DETECTORS l
l The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core.
The OPERABILITY of this system is demonstrated by irradiating each detector used and determining the acceptability of its voltage curve.
For the purpose of measuring Fg(Z) or F"m, a full incore flux map is used.
Quarter-core flux maps, as defined in WCAP-8648, June 1976, may be used in re-calibration of the excore neutron flux detection system, and full incore flux maps or symmetric incore thimbles may be used for monitoring the Quadrant Power Tilt Ratio when one Power Range Channel is inoperable.
3/4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available to promptly determine the i
magnitude of a seismic event and evaluate the response of those features important to safety.
This capability is required to permit comparison of the measured response to that used'in the design basis I
for the facility and is consistent with the recommendations of Regulatory Guide 1.12, " Instrumentation for Earthquakes."
BEAVER VALLEY - UNIT 2 B 3/4 3-5 Amendment N692
t '.
NPF-73 3/4.3 INSTRUMENTATION 1
BASES 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION j
The OPERABILITY of the meteorological instrumentation ensures that I
sufficient meteorological data is available for estimating potential j
rediation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere.
This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with
)
the recommendations of Regulatory Guide 1.23, "Onsite Meteorological i
Programs."
1 3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutd wn and maintenance of HOT STANDBY of the facility from locations outside of the control room.
This capability is required in the event control room I
habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.
3/4.3.3.6 (This Specification number is not used).
3/4.3.3.7 CHLORINE DETECTION SYSTEMS The OPERABILITY of the chlorine detection systems ensures that sufficient capability is available to promptly detect and initiate protective action in the event of an accidental chlorine release.
This capability is required to protect control room personnel and is consistent with the recommendations of Regulatory Guide 1.95,
" Protection of Nuclear Power Plant Control Room Operators Against an
~
Accidental Chlorine Release," January 1977.
3/4.3.3.8 ACCIDENT MONT'fGRING_ INSTRUMENTATION The OPERABILITY of the accident monitoring ' instrumentation ensures that sufficient information is available on, selected plant parameters to monitor and assess these variables during and following an l
accident.
This capability is consistent with the recommendations of Regulatory Guide 1.97,
" Instrumentation for Light-Water-cooled l
Nuclear Plants to Assess Plant Conditions During and Following.an Accident," December 1975 and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Tern Recommendations."
BEAVER VALLEY - UNIT 2 B 3/4 3-6 Amendment No.92 t
l
~
? *.
NPF-73 j
3/4.3 INSTRUMENTATION
, BASES 3/4.3.3.11 EXPLOSIVE GAS MQ]il,TORING INSTRUMENTATION This instrumentation includes provisions for monitoring (and controlling).the concentrations of potentially explosive gas mixtures in the waste gas holdup system.
The OPERABILITY and use of this-instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
3/4.3.4 TURBINE OVERSPEED PROTECTION This specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed.
Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety related components, equipment or structures.
l l
l l
BEAVER VALLEY - UNIT 2 B 3/4 3-7 Amendment No. 92 l
_