ML20078M049
| ML20078M049 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 01/31/1995 |
| From: | Larson C, Raftery R, Visweswaran S GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20078M008 | List: |
| References | |
| MDE-81-0485-NP, MDE-81-485-NP, NUDOCS 9502130218 | |
| Download: ML20078M049 (31) | |
Text
(ql:f h't-GENERAL ELECTRIC COMPANY c.
t MDE-81-0485-NP DRF A31-00001 JANUARY 1995 i
TECHNICAL SPECIFICATION IMPROVEMENT ANALYSIS FOR THE REACTOR PAOTECTION SYSTEM FOR BRUNSWICK STEAM EL.CTRIC PLANT,
[
UNITS 1 &. 2 (THIS REPORT HAS BEEN PREPARED FOR CAROLINA POWER & LIGHT (CP&L) THROUGH THE TECHNICAL SPECIFICATION IMPROVEMENT COMMITTEE OF THE BWR OWNERS' GROUP)
~
t PREPARED BY:
R. P. Raftery, Prin%1 Efigineer VERIFIED BY:
i C. L Lamon, Principal Engineer i
t 4
b*
A APPROVED BY:
S. Visweswaran, Project Manager Brunswick Surveillance Interval Extension Program P
I h IMDCK228 950232 05000324 P
p-..
4 GENERAL ELECTRIC COMPANY
~
MDE-81-0485-NP i
j l
l
.j.
GENERAL ELECTRIC COMPANY
' MDE-81-0485-NP
?
TABLE OF CONTENTS EAEC 1.
INTRODUCTION 1
2.
EVALUATION METHOD 2
3.
RESULTS OF RPS EVALUATION 4
4.
SUMMARY
AND CONCLUSIONS 8
i I
5.
REFERENCES 9
APPENDIX A:
RPS EVALUATION FOR THE BRUNSWICK A-1 STEAM ELECTRIC PIANT, UNITS 1 AND 2 i
l 1
- ii -
j GENERAL ELECTRIC COMPANY E
MDE-81-0485-NP 1.
INTRODUCTION This report extends the generic study of modifying the technical specification l
requirements of the Reactor Protection System (RPS) on a plant specific basis for Brunswick Steam Electric Plant, Units 1 and 2 (BSEP). The generic study (Reference 1) provides a technical basis to modify the surveillance test frequencies and allowable outef-service times of the RPS from the generic technical specifications. The generic study also provides additional analyses of various known different RPS configurations to support the application of the generic basis on a plant specific basis. The generic basis and the supporting analyses were utilized in this plant specific evaluation. The results of the l
plant specific evaluation for BSEP are presented herein.
The original report was completed in April 1985. This Revision 1 incorporates changes made to the plant since that time.
4 GENERAL ELECTRIC COMPANY MDE-81-0485-NP 2.
EVALUATION METHOD The plant specific evaluation of the modification of the surveillance test frequencies and allowable outef4ervice time of the RPS was performed in the following steps:
Obtain plant specific information on the RPS from CP&L The information a.
includes the following:
(1) Elementary Diagrams of the RPS and related systems.
1 (2) RPS descripdons such as plant Final Safety Analysis Report (FSAR).
(3) Technical specifications on the RPS.
(4) RPS surveillance test procedures.
The latest revisions ofItems I,2 and 3 above were supplied by CP&L. Item 4 above was provided by CP&L in the form of a questionnaire identifying the differences between the procedure used in the generic evaluation and the procedure used at BSEP.Section I of the checklist in Appendix A was used to identify the data source of the plant specific information.
b.
Construct the plant specific RPS configuration from the plant specific information. Sections "A" through "H" in Section II of the checklist were used l
for this process.
c.
Compare the plant specific RPS configuration with the generic RPS configuration using the generic RPS elementary diagram, RPS description, technical specification requirements, and other generic inputs.Section III of the checklist was used for this process.
GENERAL ELECTRIC COMPAhY
_ MDE-81-0485-NP d.
Classify the differences into three categories:
(1) Obvious items which have no effect on the reliability of the RPS.
Examples of these "no effect" items are component name differences, symbol differences, and other minor non-functional differences.
Disposition of the obvious "no effect" items does not require additional analysis.
(2) Potential differences which require considerable engineeringjudgment for disposition because of the functional differences. Examples of these potential differences are separate channels for manual scram as opposed to non-separate channel in the generic plant and dual redundant contacts per sensor relay in the applicable trip channels as opposed to a single set of contacts in the generic plant. The disposition of such items would require engineering assessment as shown in Appendix K of Reference 1.
(3) Potential differences which require additional analyses to evaluate the effect on the RPS failure frequency. Examples ofsuch potential differences are using HFA relays as opposed to using Potter and Brumfield relays and Agastat relays in the generic evaluation. Disposition of these items would require additional analyses to compare with the generic results. These analyses are documented in Reference 1.
Compile a list of plant specific differences of Categories (2) and (3).
e.
f.
Assess the reliability effect of the differences identified in Step (e) on the generic results. The results of the assessment are documented in Section III of the checklist.
g.
Document the results of the plant specific evaluation.
The above seven step process is documented in Appendix A of this report.
1 i i
GENERAL ELECTRIC COMPAIW MDE-81-0485-NP
- 3. RESULTS OF RPS EVALUATION The results of the plant specific evaluation of the RPS for BSEP are documented in Appendix A of this report. The results show that the RPS configuration of BSEP has the following differences which are classified Category (2) or (3):
4
t 1
GENERAL ELECTRIC COP..Ny MDE-81-0485-NF k
l l,
I
e,.
GENERAL ELECTRIC COMPANY MDE-81-0485-NP 9
9 1
I 1 l l
I l
GENERAL ELECTRIC COMPANY J
MDE-81-0485-NP 1
I
GENERAL ELECTRIC COMPANY MDE-81-0485-NP -
4.
SUMMARY
AND CONCLUSIONS 1
1 l
A plant specific evaluation of modifying the surveillance test frequencies and allowable out-of+enice time of the RPS from the technical specifications of BSEP has been performed. The evaluation utilized the generic basis and the additional analyses documented in Reference 1 The results indicated that the RPS configuradon for BSEP has several differences compared to the RPS configuration in the generic evaluation.
These differences and the assessment of their effects on the RPS failure frequency are shown in Appendix A. The analysis reported in Reference 1 shows that these differences would not significantly affect the improvement in plant safety due to the changes in the technical specifications based on the generic analysis. Therefore, the generic analysis in Reference 1 is applicable to BSEP.
l 1
P i
e i
I 5
f i
i l
9
! i
eHM
+ - - - -
ba, a
,-A
+
JL a
u i
GENERAL ELECTRIC COMPANY I
~
MDE-81-0485-NP j
1
. 5.
REFERENCES (1) " Technical Specification Improvement Analyses for BWR Reactor Protection System", General Electric Company, NEDC 30851P, May 1985.
l l
i l
t t
9 5
P I
f P
i r
)
i I
)
I,
i i
e
--s--
.-r.-
n
GENERAL ELECTRIC COMPAhY MDE-81-0485-NP L
l 1
i APPENDIX A RPS EVALUATION CHECKLIST FOR BRUNSWICK STEAM ELECTRIC PIANT, UNITS 1 AND 2 i
h P
r r
i k
=
GENERAL ELECTRIC COMPANY MDE-81-0485-NP Section I-RPS Plant Specific Data Source
]
Utility:
Carolina Power & Light 1
Plant:
Brunswick Steam Electric Plant, Units 1 & 2 1
Source Number 1.
RPS Elementary 791E414RM. Rev 18.15 sh.
2.
RPS IED 731E624BB. Rev. 7. sh. 2 and 3 (of 3) 3.
RPS MG Set Control System Elementary 944E683. Rev.1. I sh.
4.
RPS Interconnection Scheme Elementary 791E415RM. Rev. 2. 3 sh.
l 5.
RPS Design Specification 22A1480AC. Rev. 7 6.
FSAR Updated FSAR.Section 7.2 7.
Technical Specifications Section 3/4.3.1 8.
Surveillance Test Procedure Checklist EDT BOA-8521 9.
Othen RPS IED. 732E174. Rev. 9. 4 sh.
10.
CP&L Fax with comments,7/20/94.
t F
F k
A-1 rr 7
~.
l GENERAL ELECTRIC COMPANY I
MDE-81-0485-NP
.s...
i Section II-RPS Configuration Data l
A.
RPS Svstem l
Data
- Data Source -
- 1. Number of trip systems 2
(1,6) l
- 2. Number oflogic channels per trip system
- For Automatic Scram 2
(1,6)
- For Manual Scram 1
(1,6) j
- 3. Power supply source for each channel MG Set (3,6)
- 4. Operation mode
- De energize to trip Yes (1,6)
- 5. logic arrangement
- one-out-of-two twice Yes (1,6)
- 6. Electrical Protection Assemblics (EPAs)
Yes (3)
- 7. Design requirement IEEE-279 (5,6) 9 i
- The numbers shown in the data source column refer to the documents listed in SecuonI.
l A-2
GENERAL ELECTRIC COMPANY J
~
MDE-81-0485-NP Section II-RPS Configuration Data B.
RPS Sensors Total Number /RPS Data Type Number Channel Source 1.
Identify the type, total number, and number per RPS channel for the following RPS sensors.
APRM Analog 6
2 (1,5)
Turbine Stop Switch 4
2 (1,5)
Valve Turbine Control Switch 4
1 (1,5)
Valve MSIV Position Switch 8
4 (1,5)
MSL Radiation Gamma Detector 4
1 (1,5)
Icel 8 (High N/A N/A N/A N/A Water Level)
Level 3 (Iow Analog 4
1 (1,5)
Water Level)
SDV Level Type 1 (Analog)
Electronic Switch 4
1 (6)
Type 2 Float Switch 4
1 (6)
High Reactor Analog 4
1 (1,5)
Pressure High Drywell Analog 4
1 (1,5)
Pressure Manual Trip Switch 4
1 (1,5)
Mode Switch Switch 4
1 (1,5)
Trip Low Condenser N/A N/A N/A N/A Vacuum i
A-3
GENERAL ELECTRIC COMPANY MDE-81-0485-NP i
Section II-RPS Configuration Data j
B.
RPS Sensors (Continued)
Data Data Source 2.
Turbine Stop Valve closure logic arrangement 3 out of 4 closure (1,6) 3.
Turbine Stop Valve closure monitoring Position switches (2,6) 4.
Turbine Control Valve fast closure monitoring Oil Pressure Switches (2,6) 5.
MSIV closure logic arrangement 3 out of 4 closure (1,6) 6.
Diversity in SDVlevel sensors i
Float switches and analog switches (6) 7.
Number of MSL 4
(2) 8.
List of available bypasses (1,5,6)
- IRM Trip Bypass Yes Noncoincident Neutron Monitoring System Yes Trip Bypass RPV High Water Level RPS Trip Bypass NotApplicable Turbine Stop Valve RPS Trip Bypass Yes Turbine Control Valve RPS Trip Bypass Yes MSIV Closure RPS Trip Bypass Yes i
SDV High Water Level Trip Bypass Yes t
Reactor Mode Switch " Shutdown" mode Trip Yes Bypass j
[
A-4 l
w
a.
GENERAL ELECTRIC COMPANY MDE-81-0485-NP 1
i Section II-RPS Configuradon Data C.
Scusor Relavs Dam Data Source 1.
Types of relays GE Type HFA (1) 2.
Number of pairs of contacts per relay in the trip 2
(1) channel 3.
List type of relay for each RPS sensor (10)
~ Potter & Brumfield Agastat HFA CR 105/305 l
MM x
Turbine Stop Valve x
4
- Turbine ControlValve x
MSIV Position x
- MSL Radiation x
Level 3 x
SDV Level x
Type 1 (Analog) x l
Type 2 (Switch) x
- High Reactor Pressure x
~
- High Drywell Pressure x
- Mode Switch Trip x
Low Condenser Vacuum N/A 1
Ixvel 8 N/A t
?
I A-5 i
I l
I' GENERAL ELECTRIC COMPANY
. MDE-81-0485-NP i
Secdon II-RPS Configuration Data i
D.
Data Data Source 1.
Types of scram contactors GE Type CR105 (10) or CR305 2.
Total number of scram contactors 8*
(1) 3.
Number of scram contactors per channel 2
(1).
- The above 8 scram contactors are for the auto trip systems only. The manual scram channels have their own scram contacton (total of 4 contactors with 2 per channel).
I E.
Air Pilot Solenoid Valves Data l
Data Source 1/
Number of solenoid valves per contrc,1 rod drive 2
(6,9) 2.
Number of solenoid operaton per valve 1
(6,9) l 4
A4
GENERAL ELECTRIC COMPANY MDE-81-0485-NP Section II-RPS Configuration Data F.
Backuo Scram Data Data Source 1.
Type of scram contactors for Backup Scram GE Type CR105 (10)
Valves or CR305 2.
Number of scram contactors per Backup Scram 6
(1)
Valve 3.
Same RPS scram contactors are used to actuate Yes (1)
Backup Scram Valves 4.
Operator mode P
- energized to trip Yes (1) 5.
Test requirement for Backup Scram Valves Not specified in (7)
Tech. Spec.
l r
3 6
l l
A-7
GENERAL ELECTRIC COMPANY MDE-81-0485-NP f
Section II-RPS Configuration Data G.
RPS Tech. Socc. Reauirements Data Source 1.
Calibration Frequency for LPRM At least once per effective full power month using the TIP (7) sptem t
2.
Calibration frequency for trip units.
Once a month (7) 3.
Frequency of Logic System Functional Tests Once per 18 months (7) 4.
Allowable time to place an inoperable channel or trip system in the tripped conditions when the number of operable channels is less than the required minimum operable channels per trip system.
Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (7) 5.
Exception to item 4.
Tech Spec does not specify exception.
(7) 6.
Allowable time to place a trip system in the tripped conditions when the number of operable channels is less than the
~
required minimum operable channels for both trip sptems.
Within I hour (7) 7.
Exception to item 6 due to surveillance test.
Two hours for surveillance (7) 8.
Complete the Table on the following page.
(7)
A-8
REACTOR PROTECTION SYSTEM INSTRUMENTATION REQUIREMENTS Minimum Operable Channel Channel Channels Per Channel Check Functional Test Calibration Trip System Generic Plant Generic Plant Generic Plant Generic Plant Funcdonal Unit Model Specific Model Specific Model Specific Model Specific Q~
y.
I. Average Power Range Monitor:
M gf
- a. Flow Biased Simulated Thermal S,D S
S/U,W S/U,W W SA,R W,Q 3
2 Power - liigh O
- b. Neutron Flux-Ifigh S
S S/U,W S/U,W W,SA W,Q 3
2
&Q Inoperative N/A-N/A W
W N/A N/A 3
2 7Q c.
S b
gh
- 2. Reactor Vessel Steam Dome S
D M
M R
R,M
- 2 2
Pressure - fligh io
- u O
- 3. Rtactor Vessel Water Level-12)w, S
D M
M R
R,M
- 2 2
K
[4 Ixvel 3
- 4. Reactor Vessel Water level-liigh, S
N/A M
N/A R
N/A 2
N/A I.evel 8
- 5. Main Steam Line isolation Valve-N/A N/A M
M R
R 4
4 Closure
- 6. Main Steam 1.ine Radiation -liigh S
S M
M R
R 2
2
- 7. Drywell Pressure-Ifigh S
D M
M R
R,M
- 2 2
- 8. Main Condenser Vacuum -Iow N/A N/A N/A N/A N/A N/A' N/A N/A
- Monthly calibration of trip units only, transmitters are calibrated at least once per 18 months.
REACTOR PROTECrlON SYSTEM INSTRUMENTATION REQUIREMENTS Minimum Operable Channel Channel Channels Per Channel Check FunctionalTest Calibration -
Trip System o
re -
Generic Plant Generic Plant Generic Plant Generic Plant Functional Unit Model Specific Model Specific Model Specific Model Specific g
- 9. Scram Discharge Volume Water h3
=
's y
1.evel-High h'Q Type 1 - Anah>g S
N/A M
Q R
R 2
2 C
g ha Type 2 - Switch N/A N/A M
Q R
R 2
2 n-m o-
- 10. Turbine Stop Valve -Closure N/A N/A M
M R
R 4
2 g
- 11. Turbine Control Valve Fast Closure N/A N/A M
M R
R 2
2 Valve Trip System Oil Pressure-(Unit Low 2:4)
- 12. Reactor Mode Switch Shutdown N/A N/A R
R N/A N/A 2
1 Position
- 13. Manual Scram N/A N/A M
Q
-N/A N/A 2
1 S= Shift M= Monthly S/U=Startup D= Daily Q= Quarterly N/A=Not Applicable W= Weekly R= Refueling Outage
l t
GENERAL ELECTRIC COMPANY l
MDE-81-0485-NP 1
l Section II-RPS Configuration Data
. H.
RPS Surveillance Tests Procedure Data Source 1.
The following components are all tested as part of an (8) individual channel functional test:
- a. Individual channel sensor (s), e.g., Transmitters and Trip Units, switches, flux or radiation sensors.
- b. Associated logic relay (s)
- c. Associated scram contactors List any plant specific differences from the above.
RESPONSE
For 1.a. above, flux sensom are generally not included in the Channel Functional Test. Additionally other sensors such as Thermocouples may not be included. These differences are consistent with the T/S definition for Channel Functional Test.
l 2.
When an individual sensor channel is in test or repair, is (8) associated logic channel tripped or is the sensor channel jumpered? State which of the two conditions applies to your plant. If any other condition exists in your plant, describe.
RESPONSE
i For repair, the logic channel is tripped. For surveillance test, the logic channel isjumpered with exception that the last check of the channel (e.g., calibration) would provide for a test of the channel with thejumper removed by performance of the Channel FunctionalTest.
4 b
I A-11
GENERAL ELECTRIC COMPANY MDE-81-0485-NP i
Section II-RPS Configuration Data H.
RPS Surveillance Tests Procedure (Continued)
Data Source I
3.
For those plants which do not place individual channels in a (8) tripped condition during test or repair, it is assumed in the GE analysis that only the individual sensor and associated logic relay is placed in an inoperable condition during test or repair of the individual channel. If this assumption is not true for i
your plant, list the components (from sensor to scram contactors) which are placed in inoperable condition during test or repair.
]
RESPONSE
This assumption is true for Brunswick.
4.
The following number ofindividual scram contactor actuations (8) are assumed in the GE analyses for each channel functional test:
contactor pair in each trip logic channel.
- b. MSIV closure channel function tests - 4 actuations per scram contactor pair in each trip logic channel.
- c. Other channel functional tests - 1 actuation per scmm contactor pair in each trip logic channel.
List any differences from the above for your specific plant
RESPONSE
4.a. - 1 actuation per scram contactor pair.
4.b. - 1 actuation per scram contactor pair.
4.c. - No difference from that stated.
i A-12 l
c.
GENERAL ELECTRIC COMPANY MDE-81-0485-NP Section II-RPS Configuration Data H.'
RPS Surveillance Tests Procedure (Continued)
Data Source 5.
Do plant procedures allow simultaneous inoperable conditions (8)
(failed condition) of diverse sensors in a given logic channel?
RESPONSE
As allowed by BSEP T/S 3.3.1.a, any number of sensors in a trip system may be inoperable provided the sensor is placed in the tripped condition. For example, a high pressure and a low level instrument in the A trip system (Al or A2) may be inoperable as long as both channels (or the A trip system) are tripped within one hour. Operation may continue indefinitely with a half-scram condition; however, both channels must be returned to operable condition prior to returning the trip system to normal.
r e
1 A-13
GENERAL ELECTRIC COMPANY MDE-81-0485-NP Section III-Assessed Reliability Effect of RPS Configuration Differences BWR Generic Model Plant Specific Difference Assessed Reliability Effect A. RPS System
- 1. Generic model has two No difference trip systems.
- 2. Generic model has two No difference logic channels per trip system for automatic scram.
- 3. During operation, the No difference trip systems are energized and trip when de-energized.
- 4. The RPS logic is one-No difference out of-two twice, i.e.,
one out of two logic channels will trip an individual system and trip of both systems is required for scram.
- 5. Generic model has No difference Electrical Protection Assemblies (EPAs).
- 6. Each RPS channel can Separate channel for be manually tripped manual scram, but each from the Control autoscram channel can also Room using the be manually tripped by manual scram circuits, interrupting the power to the RPS.
b A-14
c GENERAL ELECTRIC COMPANY MDE-81-0485-NP Section III-Assessed Reliability Effect of RPS Configuration Differences BWR Generic Model Plant Specific Difference Assessed Reliability Effect B. Sensors
- l. Generic model has No difference Analog Trip Unit / Transmitter for pressure and level sensors.
- 3. Generic model has Six APRM moniton with eight APRM monitors two monitors shared by two with two per RPS channels.
channel.
- 4. Stop Valve Closure trip No difference logic is a reduced two-of-four required for trip.
- 5. Stop Valve Closure is No difference monitored by limit switches.
- 6. Turbine Control Valve No difference fast closure is monitored by control oil pressure.
- 7. MSIV closure trip logic No difference requires isolation of three out of four steam lines to scram.
- 8. Generic model has a No level 8 trip Ixvel 8 (High Reactor Water Level) Trip.
A-15
O 4
GENERAL ELECTRIC COMPANY MDE-81-0485-NP Section III-Assessed Reliability Effect of RPS Configuration Differences BWR Generic Model Plant Specific Difference Assessed Reliability Effect B. Sensors (Cont'd)
- 9. Generic model has DifTerent type of switches diverse Scram are used to provide Discharge Volume diversity.
(SDV) level sensors.
- 10. Generic model has 4 No difference main steamlines.
I1. Generic model does No difference not have a direct scram on low condenser vacuum.
C. Sensor Relays
- 1. For all transients there All scmm variables have are at least two scram HFA type relays.
variables with different type logic relays (either AGASTAT or Potter & Brumfield).
- 2. Each sensor relay has a Each sensor has two pairs of single pair of contacts contacts in the applicable in the applicable trip trip channel, channel.
l D. Scram Contactors
- 1. All Scram Contactors BSEP Units 1 & 2 use both are one type (GE Type GE Type CR105 & GE Type CR105).
CR305 Scram Contactors.
- 2. Eight scram contactors No difference (two per RPS channel) perform the trip function.
1 1
A-16 1
o GENERAL ELECTRIC COMPANY MDE-81-0485-NP Section III-Assessed Reliability Effect of RPS Configuration Differences BWR Generic Model Plant Specific Difference Assessed Reliability Effect E. Air Pilot Solenoid Valves
- 1. Generic model has Two HCU valves with single dual solenoid solenoid operators.
operators for each Tripping of both valves is individual HCU air required for individual pilotvalve. De-control rod scram.
energizing both solenoids results in a scram of the individual control rod.
F. Backup Scram
- 1. Actuation of Backup Back-up scram valves Scram Valves are actuations are controlled by controlled by same scram contactors from both output scram the manual and autoscram contactors as RPS.
system.
- 2. Trip logic for backup No difference scram valves is an energized to trip versus de-energized to trip forindividual HCU air pilot valves.
- 3. Backup scram valves Test requirements for the are tested during backup scram valves are not shutdown atleast once specified in the plant per 18 months.
Technical Specifications.
A-17
y
- s GENERAL ELECITIC COMPANY MDE-81-0485-NP Secdon III-Assessed Reliability Effect of RPS Configuration Differences BWR Generic Model Plant Specific Difference Assessed Reliability Effect G. Technical Specificadons and Surveillance Test Procedure:
- 1. Generic Model uses See Section II.G of this BWR6 Standard Appendix for plant specific Technical differences.
Specifications which requires:
Allowable outof-service time: I hr Test time: 2 houn Test frequency:
1W for APRM 1M for others Calibration Frequency:
IM for trip units R for transmitters
- 2. Generic Model One actuation per scram assumes two actuations contactor pair is performed per scram contactor for all channel funcdonal pair in each trip logic tests of all scram variables.
channel for the APRM The total actuations are channel functional test esdmated to be 148 per year and four actuations for for each scram contactor.
the MSIV Closure Channel functional tests, and one actuation for the other scram variables. This leads to 272 total actuations of each scram contactor per year.
A-18