ML20125C996
| ML20125C996 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/04/1992 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20125C999 | List: |
| References | |
| NUDOCS 9212140216 | |
| Download: ML20125C996 (14) | |
Text
. _.
>3 Rf Og It g
UNITED STATES NUCLEAR REGULATORY COMMISSION i
WASHINoTON o.C. 20 lie 6
\\...../-
. CAROLINA POWER & LIGHT COMPANY. et al.
DOCKET NO. 50-325 PJUNSWICKJIIRLfMITRIC PLANT. UNIT 1 AMENDHENT TO FACILITY OPERAIL@ LICENSE Amendment No.159 License No. DPR-71 l.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application-for amendment filed by Carolina Power & Light Company (the licensee), dated August 25, 1992, complies with the standards and-requirements of the Atomic Energy Act of 1954,-as amended (the Act),
. i and the Commission's rules and regulations set forth.in 10 CFR Chapter 1;
B.
The facility will operate in conformity with the appilcation, the.
provisions of the Act, and the rules and regulations of the Commission; C.
1here 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 requirements 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 Operating License No. DPR-71 is hereby amended to read as follows:
.(2) Technical Specifications
- The Technical: Specifications contained in Appendices A and B, as revised through Amendment No.159, are hereby incorporated in;the-license.
Carolina Power & Light Company shall. operate the facility in.
accordance with the Technical Specifications.
4
.p.
- w-
-.3-, * -., -, d w-w s
+,
e w
r e-v
. 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION f
4+. :' m Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects - I/II ffice of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 4, 1992 i
t t
ATTACHMENT TO LICENSE AMENDMENT NO.159 FACilfTY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-325 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised areas are indicated by marginal lines.
Remove t ggs Insert _Paaes 3/4 1-6 3/4 1-6 3/4 1-7 3/4 1-7 3/4 2-3 3/4 2-3 3/4 2-4 3/4 2-4 m
_-,.y...,...
_ ~ _ ~. -. -. - - -. - - - -. -
. - -. -.. - ~ ~ -.
t t
e REACTIVITY CONTROL SYSTEMS CONTROL ROD AVERAGE SCRAM INSERTION TIMES L.1,MITING CONDITIONS FOR OPERATION i
3.1.3.3 The average scram insertion time of all OPERABLE control rods from the fully withdrawn position, based on de-energization of the scram pilot valve solenoids as time zero, shall not exceed any of the following:
Position Inserted From Average Scram Inser.
Fully Withdray tion Tiga (Seconds)
^
46 0.358 36 1.096 26 1.860 6
3.419 APPLICABILITY; OPERATIONAL CONDITIONS 1 and 2.
ACTION:
With the average scram insertion time exceeding any of the above limits, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REOUIREMENTS 4.1,3.3 All control rods shall be demonstrated OPERABLE by scram time testing from the fully withdrawn position as required by Surveillance Requirement 4.1.3.2.
BRUNSWICK - UNIT 1 3/4 1-6 Amendment No. 169
. -.~
_.,..__.._-....~..-__..u......_.
. ~ - ~ _ _ -.. - -..
Ad I 1'
I REACTIVITY CONTROL SYSTEMS f
FOUR CONTROL ROD CROUP SCRAM INSERTION TIMES LIMI'ING CONDITION FOR OPERATION 3.1.3.4 The average scram insertion time, from the fully withdrawn position, for the three fastest control rods in each group of four control rods arranged in a two.by-two array, based on deenergization of the scram pilot valve solenoids as time zero, shall not exceed any of the following:
?
Position Inserted From Average Scram Inser-Fully Withdrawn tinp Time lSeconds) i L
46 0.379 l
36 1.162 26 1.971 6
3.624 APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.
ACTION:
With the average scram insertion times of control rods exceeding the-above limits, operation may continue and the provisions of Specification 3.0.4 are not applicable provided:
a.
The control rods with the slower than average scram insertion times are declared inoperable, b
The requirements of Specification 3.1.3.1 are satisfied, and c.
If within the preset power level of the RWM, the requirements of Specification 3.1.4.1.d are also satisfied, nnd d.
The Surveillance Requirements of Specification 4.1.3.2.c are performed at least once per 92 days when operation is continued with three or more control rods with slow scram insertion times.
Otherwise, be in at least_ HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILIANCE REQUIREMENTS i
4.1.3,4 All control rods shall be demonstrated OPERABLE by scram time testing from the fully withdrawn position as required by Surveillance Requirement -4.1.3.2.
BRUNSWICK - UNIT.1 3/4 1-7 Amendment No.159
,e-e-r+=fr.,,,-e,
,.-ne--
c--.,-
.--r.,
ym..
-r.-m wa r
wcwp-..--f-,ym,w
,----.,ec-w.,,,wpwvn-,-.erm,n--vw--rww.
-y,,,-f6g r
cis miweT w e -w - i
t t
- l POWER DISTRIBUTION LIMITS 3/4.2.7 MINIMUM CRITICAL POWER RATIO (ODYN OPTION B)
LIMITING CONDITION FOR OPERATION i
3.2.2.2 For the OPTION B MCPR limits provided in the CORE CPERATING LIMITS REPORT to be used, the cycle average 206 (notch 36) scram time (r-shall be
~
less than or equal to the OPTION B scram time limit (ts), where r *"*)and rg are determined as follows:
n I
Nr i-1 gy "h"#*
f,y, N'
n I
i-1 1 - Surveillance test number, n - Number of surveillance tests performed to date in the cycle (including BOC),
h Ni - Number of rods tested in the i surveillance test, and ri - Average scram time to notch 36 for surveillance test i N
1/2 y
r - 9 + 1.65 (a), where:
3 n
N 1
E i-1 1 - Surveillance test number n - Number of surveillance tests performed to date in the cycle (including BOC),
h Ni - Number of rods tested in the i surveillance test N3 - Number of rods tested at BOC, p - 0,830 seconds l.
(mean value for statistical scram time distribution from de-energization of scram pilot valve solenoid to dropout on l
notch 36).
o - 0.019' seconds-
- l.
(standard deviation of the above statistical distribution)
APPLICABILITY:
OPERATIONAL CONDITION 1, when THERMAL POWER is greater-than or i
equal to 25% RATED THERMAL POWER.
BRUNSWICK - UNIT 1 3/4 2-3 Amendment No. 159 rc
.,-,.--.m.
~.,,,. _ -,
~
y y
4-
...-Ev..r c #,- n -._,
~
. +
POWER DISTRIBUTION LIMITS l
LJMITING CONDITIONS FOR OPEEATION (Continued) i l
ACTION:
Within twelve hours after determining that r is greater than r, the a
operating limit MCPRs shall be either:
Adjusted for each fuel type such that.the operating limit MCPR in a.
the maximum of the non pressurization transient MCPR operating limit specified in the CORE OPERATING LIMITS REPORT or the l
adjusted prescuritation transient MCPR operating limits, where i
the adjustment is made by:
r
-r ave B
- MCPR 4
(MCPR MCPR
)
adjus ted option B r
-r option A option B A
B where:
r3 - 1.096 seconds, control rod average scram insertion time l
limit to notch 36 per Specificacion 3.1,3.3,.
MCPR-
- Specified in the CORE OPERATING LIMITS REPORT, MCPR E ' " ^ - Specified in the CORE OPERATING LIMITS REPORT, or, option B b.
The OPTION A MCPR limits specified in the CORE OPERATING LIMITS REPORT.
SURVEILLANCE REOUIREMENTS 4.2.2.2-The values of r.,,and re shall be determined and compared each time a scram time test is performed.
The requirement for the _ frequency of scram time testing shall be-identical to Specification 4.1.3.2.
?
BRUNSWICK UNIT 1-3/4 2-4 Amendment-No.1591
.x, ~ u.a
p*"
f
UNITED STATES
/g NUCLEAR REGULATORY COMMISSION WASHINGloN. D.C. 20146
%...../
CAROLINA POWER & LIGHT COMPANY. et al.
DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT. UNIT 2 3
AMENDMENT TO FACILITY OPERATING LICENS1 Amendment No.190 License-No. DPR,
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by Carolina Power & Light company (the licensee), dated August 25, 1992, 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;
8.
The facility will operate in conformity with the application, the-provisions of the Act, and the rules and regulations of the Commission; a
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 requirements 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 Operating License No. DPR-62 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in A)pendices A and.B, as.
revised through Amendment No.190, are here)y incorporated in the license.
Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.
,n-,
, +
,.7-u p,
en-
--n.-
Ewr
,~-- --
e <
~
v-w
n s 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of issuance.
~
FOR TliE NUCLEAR REGULATORY COMMISSION N
Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 4, 1992 i
i er b
5 ATTACHMENT TO LICENSE AMENDMENT NO. 190 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised areas are indicated by marginal lines.
Remove Paaes insert Paaes 3/4 1-6 3/4 1-6 3/4 1-7 3/4 1-7 l
3/4 2-3 3/4 2-3 l
3/4 2-4 3/4 2-4 l
l l
l l
l l
l l
l l
~
}_tEACTIVITY CONTROL SYSTEMS CONTROL ROD AVERAGE SCRAM INSERTION TIMES LIMITING CONDITIONS FOR OPERATION 3.1.3.3 The average scram insertion time of all OPERABLE control rods from i
the fully withdrawn position, based on de energization of the scram pilot valve solenoids as time zero, shall not exceed any of the folicwing:
Position Inserted From Average Scram Inser.
l
_ Fully Withdrawn tion Time (Seconds) 46 0,358 36 1.096 26 1.860 6
3,419 APPLICABILITY:
OPERATIONAL CONDITIONS 1 ar.d 2.
ACTION:
With the average scram insertion time exceeding any of the above limits, be in at least HOT $HUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILIANCE REOUIREMENTS 4.1.3.3 All control rods shall be demonstrated OPERABLE by scram time testing.
from the fully withdrawn position as required by Surveillance Requirement 4.1.3.2.
BRUNSWICK - UNIT 2 3/4 1 6 Amendment No.190
.' It
,.- J e.,.
,,...-.v
,s,
-,.4
, ~.,. -. - - - - - -.. _
,,..,_...,J.~.
J......
J._.,'
. -.~.-. _ - - --.
E 1
i REACTIVITY CONTROL SYSTEMS FOUR CONTROL ROD CROUP SCBAM INSERTION TIMES I
LIMITING CONDITION FOR OPERATION 3.1.3.4 The average scram insertion time, from the fully withdrawn position, for the three fastest control rods in each group of four control rods arranged-in a t co by two array, based on deenergization of the scram pilot valve soleno
..s as Line zero, shall not exceed any of the following:
i Position Inserted Ec ?
' Average Scram Inser-Fully Withdrawn tion Time (Seconds';
46 0.379 36 1.162 26 1.971 6
3.624 APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.
i ACTION:
With the average scram insertion times of control rods exceeding the above I
limits, operation may continue and the provisions of Specification 3.0.4 are not applicable provided:
I a.
The control rods with the slower than average scram insertion times i
are declared inoperable, I
l b.
The requirements of Specification 3.1.3.1 are satisfied, and I
c.
If within the preset power level of the RWM, the requirements of Specification 3.1,4.1.d are also satisfied, and-d.
The Surveillance Requirements-of Specification 4.1.3.2.c are performed at least once per 92 days when operation is continued with three or more control rods with slow scram inset tion t?.mes.
Otherwise, be in at least HOT SHUTDOWN within the next-12 hours.
l l
SURVEILIANCE REQUIREMENTS l
t 4.1.3.4 All control rods shall be demonstrated OPERABLE by scram _ time testing from the fully withdrawn position as required by _ Surveillance Requirement 4.1.3.2.
BRUNSWICK - UNIT 2 3/4 1 7 Anendment No.190 '
D-PN-fa te' et-'kT-De Tw-r,
%wsm-
- ,n.www--
34g,w=me-wwer ws vmw'E-A was 1 R *v t'yye w
tyt--W'1vW+--
T' P'99-M"*T-Nvvt 4--W r
- -+W=+
m
( (
f k k'v't'p *w e FP 7 T-O' N y
-'N-O'99 Wy q 8q T q"ar FT* - k g-ng
POWER DISTRIBUTION LIMITS 3/4.2.2 MINIMUM CRITICAL POWER RATIO (ODYN OPTION B)
LIMITING CONDITION FOR OPERATION 3.2.2.1 For tha OPTION 3 MCPR limits provided in the CORE OPERATING LIMITS REPORT to be used, the cycle average 204 (notch 36) scram time (r shall be less than or equal to the OPTIO!! B reram rime limit (r ), where r ***)and r s
s are determined as follows:
n E
Nr i-1 gg r,ye -
n N g E
i 1-1 i
i - Surveillance test number, n - Number of surveillance tests n
.med to date in the cycle (including BOC),
g N1 - Number of rods tested in the i surveillance test, and ri - Average scram time to notch 36 for surveillance test i 9-l1/2 N
1
- p + 1.65 (a), where:
f B
n N
I E
i 1-1 1 - Surveillance test number i
n - Number of surveillance tests performed to date in the cycle (including B00),
g N - Number of rods tested in the i surveillance test iNt - Number of rods tested at BOC,
- 0.830 seconds l'
(mean value for statistical scram time distribution from l
de-energization of scram pilot valve solenoid to dropout on-l notch 36),
o - 0.019 seconds l-(standard deviation of the above statistical distribution) i APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 25% RATED THERMAL POWER.
BRUNSWICK - UNIT 2 3/4 2-3 Amendment No.190 -
f a
n
,,A-lm.
.. - -. - ~.
_. -. - -. - -. ~ -.. -
, -... - ~ _.,
t POWER DISTRIBUTION LIMITS i
LIMITING CONDITIONS FVR OPERATION (Continued)
ACTION:
i Within twelve hours after determining that r is greater than r, the s
operating limit MCPRs shall be either:
Adjusted for each fuel type such that the operating limit MCPR is a.
the maximum of the non pressurization transient MCPR operating
~
limit specified in the CORE OPERATING LIMITS REPORT or the adju ed pressurization transient MCPR operating limits, where the adjustment is made by:
r r
ave B
- MCPR
+
(MCPR
- MCPR
)
adj usted option B r
-r option A option B A
B a - 1.096 seconds, control rod average scram insertion time.
l where:
r limit to notch 36 per Specification 3.1.3.3, MCPR Ption A _.Specified in the CORE OPERATING LIMITS REPORT, MCPR Specified in the CORE OPERATING' LIMITS REPORT, or, option B b.
The OPTION A MCPR limits specified in the CORE OPERATING LIMITS -
REPORT.
SURVEILLANCE REOUIREMENTS 4.2.2.2 The values of r,,, and te shall be determined and compared each time a scram time test is performed.
The requirement for the frequency of scram time testing shall be identical to Specification 4.1.3.2.
l h
.2RUNSWICK - UNIT 2 3/4 2-4
. Amendment No.190 :
_,__. _..,_ _.J