ML20058L106
| ML20058L106 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/08/1993 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20058L094 | List: |
| References | |
| NUDOCS 9312160144 | |
| Download: ML20058L106 (5) | |
Text
,
ENCLOSURE 4 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50-325 & 50-324 OPERATING LICENSE NOS. DPR-71 & DPR-62
'l REQUEST FOR LICENSE AMENDMENT-i NUMAC STEAM LEAK DETECTION EQUIPMENT LICENSE AMENDMENT CORRECTED PAGES j
PAGE CHANGE INSTRUCTIONS UNIT 1 l
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3/4 3-29 3/4 3 i i
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PDR ADOCK 05000324 t.
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ENCLOSURE 5 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 j
NRC DOCKET NOS. 50-325 & 50-324 OPERATING LICENSE NOS. DPR-71 & DPR-62 REQUEST FOR LICENSE AMENDMENT NUMAC STEAM LEAK DETECTION EQUIPMENT LICENSE AMENDMENT i
CORRECTED PAGES t
_ TECHNICAL SPECIFICATION PAGE - UNIT 1 i
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TABLE 4.3.2-1 (Continued) 52 ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS Y:
CHANNEL OPERATIONAL 55 CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH
-4 TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED
~
4, CORE STANDBY COOLING SYSTEMS ISOLATION a.
High Pressure Coolant Injection System Isolation 1.
HPCI Steam Line Flow - High Transmitter:
NA")
NA R*)
1, 2, 3 Trip Logic:
D H
H 1,2,3 2.
HPCI Steam Line High Flow to 2:
Time Delay Relay NA R
R 1,2,3 3.
HPCI Steam Supply Pressure - Low NA M
R 1,2,3 4.
HPCI Steam Line Tunnel Temperature High NA SA R
1,2,3 l
5.
Bus Power Monitor NA R
NA 1,2,3 6.
HPCI Turbine Exhaust Diaphragm Pressure High NA H
Q 1,2,3 7.
HPCI Steam Line Ambient Temperature - High NA SA R
1,2,3 l[
8.
HPCI Steam Line Area g
A Temperature - High NA SA R
1,2,3 s
9.
HPCI Equipment Area
((
Temperature - High NA SA R
1,2,3 O
- 10. Drywell Pressure - High Transmitter:
NA"'
NA R*'
1, 2, 3 Trip Logic:
D H
H 1,2,3
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ENCLOSURE 6 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50-325 & 50-324 i
OPERATING LICENSE NOS. DPR-71 & DPR-62 i
REQUEST FOR LICENSE AMENDMENT
{
NUMAC STEAM LEAK DETECTION EQUIPMENT LICENSE AMENDMENT l
CORRECTED PAGES I
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TECHNICAL SPECIFICATION PAGE - UNIT 2 i
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TABLE 4.3.2-1 (Continued)
El ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL 25 CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH
-4 TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED ro
- 4. CORE STANDBY COOLING SYSTEMS ISOLATION a.
High Pressure Coolant Injection System Isolation 1.
HPCI Steam Line Flow High Transmitter:
NA"'
NA R*'
1, 2, 3 Trip Logic:
D M
M 1,2,3 2.
HPCI Steam Line Flow - High to 3:
Time Delay Relay NA R
R 1,2,3 3.
HPCI Steam Supply Pressure - Low NA M
R 1,2,3 4.
HPCI Steam Line Tunnel Temperature - High NA SA R
1,2,3 l
5.
Bus Power Monitor NA R
NA 1,2,3 6.
HPCI Turbine Exhaust Diaphragm Pressure - High NA M
Q 1,2,3 7.
HPCI Steam Line Ambient Temperature - High NA SA R
1,2,3 EI 8,
HPCI Steam Line Area l[
A Temperature - High NA SA R
1,2,3 e
9.
HPCI Equipment Area ll Temperature - High NA SA R
1,2,3 O
- 10. Drywell Pressure High
~
Transmitter:
NA"'
NA R*)
1, 2, 3 Trip Logic:
D M
M 1,2,3
CP&L Carolina Power & Light Company P O Box 104?9 Southpod NC 28461 SERIAL: BSEP-93-0185 Roy A ANDERSON 10 CFR 50.90 we e,esem n,unse nuacm ryam TSC 93TSBO7 Unitei States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 REQUEST FOR LICENSE AMENDMENT NUMAC STEAM LEAK DETECTION EQUIPMENT LICENSE AMENDMENT - CORRECTED PAGES Gentlemen:
In accordance with the Code of Federal Regulations, Title 10, Parts 50.90 and 2.101, Carolina Power & Light Company (CP&L) hereby requests a revision to Appendix A of Operating Licenses DPR-71 and DPR-62 (the Technical Specifications) for the Brunswick j
Steam Electric Plant (BSEP), Units 1 and 2.
I The proposed change corrects Technical Specification pages issued for Amendment 166 for Brunswick Unit 1 and Amendment 197 for Brunswick Unit 2, regarding NUMAC Steam j
Leak Detection Equipment. Specifically, on page 3/4 3-29 for each unit, the Channel Calibration frequency of Item 4.a.4, HPCI Steam Line Tunnel Temperature - High, was inadvertently lef t as quarterly (Q) rather than being revised to refuel (R). The text of CP&L's September 14,1992 license amendment request and the NRC's safety evaluation i
for Amendments 166 and 197, dated October 14,1993, addressed the frequency change from quarterly to refuel for this item. However, the revised pages provided with the September 14,1992 license amendment request and the typed pages provided on September 21,1993 did not reflect the requested change. provides a detailed description of the proposed change and the basis for the i
change. details, in ecordance with 10 CFR 50.91(a), the basis for the Company's determination that the proposed change does not involve a significant hazards consideration. provides an environmental evaluation which demonstrates that the proposed -
amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental assessment needs to be prepared in connection with issuance of the amendment.
.,f_j / M O b T PP.
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Document Control Desk BSEP-93-0185 / Page 2 l
! 'provides page change instructions for incorporating the proposed revisions.
l provides the typed Technical Specification page for Unit 1.
! provides the typed Technical Specification page for Unit 2.
Carolina Power & Light Company is providing, in accordance with 10 CFR 50.91(b),
i Mr. Dayne H. Brown of the State of North Carolina with a copy of the proposed license l
j amendment, i
Carolina Power & Light Company requests that these corrected pages be included with the next license amendment scheduled to be issued, which the Company understands will be j
the Core Alterations amendments (NRC TAC Nos. M85162 & M85163). These revised Technical Specification pages should be effective as of the date of issuance of the amendment anti to be implemented within 60 days for Unit 1 and to be effective and implemented upon completion of refueling outage 10 (B211R1) for Unit 2.
l Please refer any questions regarding this submittal to Mr. W. Levis at (910) 457-2404.
I Very truly yours, i
/
fl.. Anderson MAT / mat (930185.000)
Enclosures R. A. Anderson, having been first duly sworn, did depose and say that the information contained herein is true and correct to the best of his information, knowledge and belief; j
and the sources of his information are officers, employees, contractors, and agents of f
Carolina Power & Light Company.
I hAr n
hiotary (Seal)- E i
My commission expires: b-th j%
cc:
Mr. Dayne H. Brown, State of North Carolina Mr. S. D. Ebneter, NRC Reg?on 11 Administrator i
Mr. P. D. Milano, NRC/NRR Senior Project Manager - BNP Mr. R. L. Prevatte, NRC Senior Resident inspector - BNP
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ENCLOSURE 1 1
i BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50-325 & 50-324 OPERATING LICENSE NOS. DPR-71 & DPR-62 REQUEST FOR LICENSE AMENDMENT NUMAC STEAM LEAK DETECTION EQUIPMENT LICENSE AMENDMENT l
CORRECTED PAGES
?
i, BASIS FOR CHANGE REQUEST i
Backnround:
The proposed change corrects Technical Specification pages issued for Amendment 166 j
for Brunswick Unit 1 and Amendment 197 for Brunswick Unit 2, regarding NUMAC Steam Leak Detection Equipment. Specifically, on page 3/4 3-29 for each unit,' the Channel Calibration frequency of item 4.a.4, HPCI Steam Line Tunnel Temperature - High, was
(
inadvertently left as quarterly (Q) rather than being revised to refuel (R). The text of 1
CP&L's September 14,1992 license amendment request and the NRC's safety evaluation for Amendments 166 and 197, dated October 14,1993, addressed the frequency change l
from quarterly to refuel for this item. However, the revised pages provided with the i
September 14,1992 license amendment request and the typed pages provided on September 21,1993 did not reflect the requested change.
l Procosed Chanae:
i i
i The Channel Calibration frequency of item 4.a.4 of Table 4.3.2-1, HPCI Steam Line Tunnel i
Temperature - High, is being revised from quarterly (Q) to refuel (R).
-l Basis:
Carolina Power & Light Company has reviewed the requested correction and determined that it is purely administrative in nature. The refuel Channel Calibration frequency for item j
4.a.4 of Table 4.3.2-1 was reviewed and approved by the NRC in the saiety evaluation for Amendments 166 and 197 dated October 14,1993.
The prr posed change merely revises e
the Channel Calibration frequency to properly reflect what has been reviewed and I
approved by the NRC.
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ENCLOSURE 2 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50-325 & 50-324 OPERATING LICENSE NOS. DPR-71 & DPR-62 REQUEST FOR LICENSE AMENDMENT NUMAC STEAM LEAK DETECTION EQUIPMENT LICENSE AMENDMENT CORRECTED PAGES l
10 CFR 50.92 EVALUATION The Commission has provided standards in 10 CFR 50.92(c) for determining whether a significant hazarc s consideration exists. A proposed amendment to an operating license for a f acility involves no significant hazards consideration if operation of the f acility in accordance with the proposed amendment would not: (1) involve a significant increase in j
the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety.~ Pursuant to 10 CFR 50.91(a)(1),.
Carolina Power & Light Company has reviewed this proposed license amendment request and determined that its adoption would not involve a significant hazards consideration.'
The basis for this determination are as follows:
{
Proposed Chance:
The Channel Calibration frequency of item 4.a.4 of Table 4.3.2-1, HPCI Steam Line Tunnel Temperature - High, is being revised from quarterly (Q) to refuel (R).
Basis:
The change does not involve a significant hazards consideration for the following reasons:
+
1.
The proposed amendment does not involve a significant increase in the probability -
or consequences of an accident previously evaluated. The proposed change corrects Technical Specification pages issued for Amendment 166 for Brunswick Unit 1 and Amendment 197 for Brunswick Unit 2, regarding NUMAC Steam Leak Detection Equipment. Specifically, on page 3/4 3-29 for each ur t, the Channel e
Calibration frequency of item 4.a.4, HPCI Steam Line Tunnet TSmperature - High,.
was inadvertently left as quarterly (Q) rather than being revised to refuel (R). The_
text of CP&L's September 14,1992 license amendment request and the NRC's safety evaluation for Amendments 166 and 197, dated October 14,1993,.
addressed the frequency change from quarterly to refuel for this item. Therefore, the proposed change is purely administrative in nature and can not involve a significant increase in the probability or consequences of an accident previously evaluated.
2.
The proposed amendment does not create tne possibility of a new or different kind i
E2-1 i
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t of accident from any accident previously evaluated. As stated above, the NRC's.
safety evaluation for Amendments 166 and 197, dated October 14,1993, addressed the frequency change from quarterly to refuel for item 4.a.4 of Table 4.3.2-1, HPCI Steam Line Tunnel Temperature - High. Therefore, the proposed change is purely administrative in nature and can not create the possibility of a new i
or different kind of accident from any accident previously evaluated.
j 3.
The proposed amendment does not involve a significant reduction in the margin of -
safety.
The proposed change corrects Technical Specification pages issued for Amendment 166 for Brunswick Unit 1 and Amendment 197 for Brunswick Unit 2, regarding NUMAC Steam Leak Detection Equipment. The NRC's safety evaluation for Amendments 166 and 197, dated October 14.1993, addressed the change of Channel Calibration frequency of item 4.a.4, HPCI Steam Line Tunnel Temperature -
High from quarterly (Q) to refuel (R). Therefore, the proposed change is purely administrative in nature and can not involve a significant reduction in the margin of safety.
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ENCLOSURE 3 d
.i BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50-325 & 50-324 OPERATING LICENSE NOS. DPR-71 & DPR-62
. REQUEST FOR LICENSE AMENDMENT NUMAC STEAM LEAK DETECTION EQUIPMENT LICENSE AMENDMcNT CORRECTED PAGES i
ENVIRONMENTAL CONSIDERATIONS 10 CFR 51.22(c)(9) provides criterion for and identification of licensing and regulatory actions eligible for categorical exclusion from performing an environmental assessment.
A proposed amendment to an operating license for a facility requires no environmental-assessment if operation of the facility in accordance with the proposed amendment would not: (1) involve a significant hazards consideration; (2) result in a significant change in the types or significant increase in the amounts of any effluents that may be released offsite;.
(3) result in an increase in individual or cumulative occupational radiation exposure.
Carolina Power & Light Company has reviewed this request and determined that the proposed amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with the issuance of the amendment. The basis for this determination follows:
Proposed Chance:
The Channel Calibration frequency of item 4.a.4 of Table 4.3.2-1, HPCI Steam Line Tunnel Temperature - High, is being revised from quarterly to refuel (R).
Basis:
The change meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) for the following reasons:
1.
As demonstrated in Enclosure 2, the proposed amendment does not involve a significant hazards consideration.
2.
The proposed amendment does not result in a significant change in the types or significant increase in the amounts of any effluents that may be released offsite.
The proposed change corrects Technical Specification pages issued for Amendment 166 for Brunswick Unit 1 and Amendment 197 for Brunswick Unit 2, regarding NUMAC Steam Leak Detection Equipment. Specifically, on page 3/4 3-29 for each unit, the Channel Calibration frequency of item 4.a.4, HPCI Steam Line Tunnel Temperature - High, was inadvertently left as quarterly (Q) rather than being revised to refuel (R). The text of The NRC's safety evaluation for Amendments 166 and E3-1 t
i 197, dated October 14,1993, addressed the frequency change from quarterly to refuel for this item. ' Therefore, the proposed change is purely administrative in nature. As such, the change can not affect the types or amounts of any effluents l
that may be released offsite.
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l 3.
The proposed amendment does not result in an increase in ind'vidual or cumulative occupational radiation exposure.
As stated above, the NRC's safety evaluation for Amendments 166 and 197, dated
.I October 14,1993, addressed the frequency change from quarterly to refuel for I
Item 4.a.4 of Table 4.3.2-1, HPCI Steam Line Tunnel Temperature - High.
l Therefore, the proposed change is purely administrative in nature and has no affect on either individual or cumulative occupational radiation exposure.
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j ENCLOSURE 4 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50-325 & 50-324 OPERATING LICENSE NOS. DPR-71 & DPR-62 l
F EQUEST FOR LICENSE AMENDMENT NUMAC STEAM LEAK DETECTION EQUIPMENT LICENSE AMENDMENT '
CORRECTED PAGES P. AGE CHANGE INSTRUCTIONS i
~I UNIT 1 i
Removed Pane Inserted Paae f
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3/4 3-29 3/4 3-29
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UNIT 2 l
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3/4 3-29 3/4 3-29 6
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ENCLOSURE 5
?
BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 l
NRC DOCKET NOS. 50-325 & 50-324 OPERATING LICENSE NOS. DPR-71 & DPR-62 REQUEST FOR LICENSE AMENDMENT NUMAC STEAM LEAK DETECTION EQUIPMENT LICENSE AMENDMENT CORRECTED PAGES I
i TECHNICAL SPECIFICATION PAGE - UiJIT 1 i
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TABLE 4.3.2 1 (Continued) g R
ISOLATION ACTUATION INSTRUMENTATION _ SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL c5 CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH H
TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED
- 4. CORE STANDBY COOLING SYSTEMS ISOLATION a.
High Pressure Coolant Injection System Isolation 5
1.
HPCI Steam Line Flow - High Transmitter:
NA")
NA R("
- 1. 2. 3 Trip Logic:
D H
M
- 1. 2. 3 L
2.
HPCI Steam Line High Flow w2 Time Delay Relay NA R
R 1, 2. 3 A,
3.
HPCI Steam Supply Pressure - Low NA M
R
- 1. 2. 3 4.
HPCI Steam Line Tunnel Temperature - High NA SA R
1,2,3
.l 5.
Bus Power Monitor NA R
NA
- 1. 2. 3 6.
'HPCI Turbine Exhaust-Diaphragm Pressure High NA M
Q 1, 2. 3 7.
HPCI Steam Line Ambient Temperature High NA SA R
- 1. 2. 3 E
-8.
HPCI Steam Line Area
(
A Temperature High NA SA R-
- 1. 2. 3 a
3 9.
HPCI Equipment Area
[
Temperature - High NA SA R
- 1. 2. 3 O
10.
Drywell Pressure - High Transmitter:
NA")
NA R'"
- 1. 2. 3 Trip Logic:
D
-H M
1, 2. 3
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ENCLOSURE 6 l
BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 I
NRC DOCKET NOS. 50-325 & 50-324
{
OPERATING LICENSE NOS. DPR-71 & DPR-62 REQUEST FOR LICENSE AMENDMENT NUMAC STEAM LEAK DETECTION EQUIPMENT LICENSE AMENDMENT CORRECTED PAGES i
i f
f 1
TECHNICAL SPECIFICATION PAGE - UNIT 2
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TABLE 4.3.2 1 (Continued) 9 ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL c5 CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH H
TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED N
- 4. CORE STANDBY COOLING SYSTEMS ISOLATION a.
iiigh Pressure Coolant Injection System Isolation 1.
HPCI Steam Line Flow High Transmitter:
NA
NA R"
1, 2, 3 Trip Logic:
D M
M 1,2,3 2.
HPCI Steam Line Flow - High w2 Time Delay Relay NA R
R 1,2,3 3.
HPCI Steam Supply Pressure - Low NA M
R 1,2,3 4.
HPCI Steam Line Tunnel Temperature - High NA SA R
1,2,3 l'
5.
Bus Power Monitor NA R
NA 1, 2, 3 6.
HPCI Turbine Exhaust Diaphragm Pressure High-NA H
Q 1,2,3 7.
HPCI Steam Line Ambient Temperature - High NA SA R
1,2,3 E
8.
HPCI Steam Line Area
[
A Temperature - High NA.
SA R
1,2,3 a
3 9.
HPCI Equipment Area
[
Temperature - High NA SA R
1,2,3 O
- 10. Drywell Pressure High
-Transmitter:
NA
NA R'6' 1, 2, 3 Trip Logic:-
0 M
M 1,2,3
..