ML20205T573
| ML20205T573 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 04/02/1987 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLR-N87050, NUDOCS 8704070326 | |
| Download: ML20205T573 (11) | |
Text
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Pubhc Service Electric and Gas Company Cctbin A. McNeill, Jr.
Public Service Electnc an(1 Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609 339-4800 Vice President -
Nuclear APR 02 TN7 NLR-N87050 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ANTICIPATED TRANSIENT WITHOUT SCRAM HOPE CREEK GENERATING STATION DOCKET NO. 50-354 PSE&G is providing, per Attachment 1 to this letter, the additional information that was requested in your letter dated February 4, 1987, regarding PSE&G's implementation of the ATWS Rule (10 CFR 50.62) requirements.
In addition to the above stated letter, a telephone conversation was held on March 11, 1987 between the NRC staff members requesting the information and members of PSE&G's engineering N
staff.
The purpose of the conversation was to clarify what additional information was being requested in the February 4, 1987 letter.
PSE&G understands the following:
Item #2 - A.
End-of-cycle (EOC) RPT System is the Reactor Protection System (RPS).
- B.
Qualified isolators are those isolators t"t3L maintain electrical isolation between 'h.
Er,
t electrical loop and the ATWS electrica?
,o-that provide recirculation pump trip signats.
Item #3 - PSE&G will provide applicable sections of the completed Preoperational Test Procedure (PTP) for the Redundant Reactivity Control (ATwS) system relating to ATWS testing.
Item #4 - Reactor Trip System (RTS) is the Reactor Protection System (RPS).
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'8704070326 870402' ~'
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PDR ADOCK 05000354.
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Item 45 - PSE&G will reference sections of the FSAR and SER when applicable.
Again, it is our understanding that the NRC is concerned with the isolators that maintain electrical isolation between the RRCS (ATWS) and the RPS, such that no one common failure to either system would prevent the other system from performing its safety function.
If you should have any questions regarding this matter, please feel free to contact us.
Sincerely, t_ _A Attachment C
Mr. D. H. Wagner USNRC Licensing Project Manager Mr.
R. W. Borchardt USNRC Senior Resident Inspector i
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l ATTACHMENT 1 Provide the following design information as supporting documentation of your method of compliance with 10 CFR 50.62:
Item 1:
"The electrical functional diagrams to indicate the recirculation pump trip (RPT) system from sensor logic to the field breaker trip coils including documentation that redundant trip coils were used for each pump."
Response
PSE&G interprets the term " field breaker" as the End-of-Cycle (EOC) Breakers downstream of the motor generator set.
Our design has two EOC breakers in series for each reactor recirculation pump (total of 4).
Each breaker has two independent trip coils, one receives a trip signal from the RPS System and the other receives a trip signal from the ATWS/RRCS System.
Both trip coils are IE qualified.
The following drawings are being provided as requested: E-0004-1, E-3043-0, E-6016-0, 762E180, 944E309AC, and 791E414AC.
Item 2:
"The drawings to indicate the interface between the end-of-cycle (EOC) RPT system and the ATWS related RPT system including documentation that qualified isolators are used between the safety related EOC-RPT signal and the ATWS-RPT signal."
Response
As stated in Item #1 above, each EOC breaker has two independent trip coils.
Trip coil number one receives a trip signal from the RPS System and trip coil number two receives a trip signal from the RRCS/ATWS System.
The lE RPS System and the lE RRCS/ATWS System are totally independent of each other, therefore, no additional qualified isolators are required.
Drawings listed in Item #1 should be used for this item.
Item 3:
"The documentation to describe the analysis and/or tests to verify that the Alternate Rod Injection (ARI) system function time will begin within 15 seconds and be completed within 25 seconds from ARI initiation."
Response: to this letter represents the applicable sections of the SA-1 Preoperational Test Procedure for the Redundant Reactivity Control (ATWS) which shows that the Alternate Rod Injection (ARI) meets the function time requirements.
Item 4:
"The electrical one-line diagram to demonstrate the electrical independence between the ARI system and the reactor trip system (RTS)."
4
Response
The Alternate Rod Injection System (ARI) is part of the RRCS/ATWS System.
As stated in Item #2 of this letter the RRCS/ATWS and the RPS Systems are independent of each other.
The RRCS/ATWS 125 VDC power is from the ESF System.
The RPS is a 120 VAC power supply system.
Per the design drawings, it should be noted that a failure of the RPS System will not prevent the safety function of the ARI System from being performed and vice-versa._ The following drawings are being provided as requested:
E-4009, 791E414AC, and 944E309AC.
Item 5:
"The qualification information on isolation devices:
a.
For the type of device used to accomplish electrical isolation describe the specific 4
testing performed to demonstrate.that the 2
device is acceptable for its application (s).
This description should. include elementary diagrams where necessary to indicate the test configuration and how the maximum credible faults were applied to the devices.
b.
Data to verify that the maximum credible faults applied during the test were the maximum voltage / current to which the device could be exposed, and define how the maximum voltage / current was determined.
c.
Data to verify that the maximum credible fault was applied to the output of the device in the transverse mode (between signal and return) and to verify that other faults were considered (i.e., open and short circuits).
d.
Define the pass / fail acceptance criteria for each type of device.
e.
Provide a commitment that the isolation devices comply with the environment qualifications (10 CFR 50.49) and with the seismic qualifications which were the basis for pla-t licensing.
f.
Provide a description of the measures taken to protect the safety systems from electrical interference (i.e., Electrostatic Coupling, EMI, Common Mode and Crosstalk) that may be generated by the ATWS circuits.
g.
Provide information to verify that the Class lE isolator is powered from a Class IE source."
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Response
As stated in Items #1 and #2 above, redundant trip coils are used for each EOC breaker and additional qualified isolators are not required for electrical isolation between the RRCS/ATWS and the RPS Systems Item 6:
The information readout to the control room operator for the ARI and the RPT systems.
Response
The information readout for the ARI and the RPT System are shown on the following drawings:
E-6794 and 944E309AC, Sht 33, 36, 39, and 44. represents a list of drawings included in this submittal.
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A'5TACHMENT 2 INITIALS /DATE
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8.3.3 INTERDIVISIONAL TESTING 8.3.3.1 At panel 10C602, request an AUTO START, and then note the cycle counter reading for - -
Division 1 and Division 2.
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8.3.3.2 Verify STS can go at least 100 counts on the y
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cycle counter for each division without g
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stopping.
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8.3.3.3 At panel 10C651, depress RRCS RESET switches M tl20 h S4A, S4B, S4C and S4D.
8.3.3.4 At panel 10C651, depress RRCS ARI RESET switches S3A, S3B, S3C and S3D.
Verify RRCS TROUBLE alarm (Dl-El) orr panel 10C800
($ 020$U c1 ears.
,i This portion of the test must be coordinated with cognizant Test Engineer of CRD Hydraulic System
..QQt_ f fo/te (PTP-BF-1).
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~ Verify all CRDHS instrumentation is aligned 8.4.1 for normal operation as per the CRDHS station operating procedure.
t_hti r/g/h 8.4.2 Verify all CRDHS valves and system boundary valves are positioned for normal operation as procedure.
Al r /q/pe per CRDHS station operatin} eh~rswMwitw%4w es>W u#
i In panel 10C609 verify {p (fduses C71-21B and A
jugpersNo9 8.4.3 (f'"g g,wi)_through 128 : in; @ l stas d 9 5/,
C71-22B are removed Mar -* p ? 2_t.:.;;.
In panel 10C611.n>U* ? ' ?s.4sW !5?k-H at.t.sxS w 4verifyAh umpers
'8.4.4
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_ fuses"C71-21B and are in:telle_ an
_throuch 16g
( p, ggSg1-22B are removed gr 3p 0.2.0.5.r:g M i M /8b ewm awywom 8.4.5 Verify that all control rods are fully N llT/8 b withdrawn.
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INITIALS /DATE
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E' 8.4.6 At panel 10C601 remove fuses F5A and F6A (ARI valves solenoids).
Reconnect the leads going from 10C601 to DIVISION 1 ARI valves in panel 10C601.
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i Valve No Connection
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IBF-SV-F160A B-TB223-4 and B-TB223-5 fera. / 9/R lbW //f//4 g
BF-SV-F162A B-TB233-4 and B-TB233-5 g F tsa,,q /pt, D/Afd//f/76
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4800 IBF-SV-Flii2C B-TB243-4 and B-TB243-5 S
eis t / t/E K fs/d s/f/f.-
$,95.#
IBF-SV-F163A B'-TB243-10 and B-TB243-ll ad, t 3 /sc t-8.4.7 At panel 10C601 reinstall fuses F5A and F6A.
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j 8.4.8 At panel 10C602 remove fuses F5B and F6B.
et4l3 sig /A 8.4.9 Reconnect the following leads:
I BF-SV-F160B B-TB223-4 and B-TB223-5l,16
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ha & & ff/fl ///h BF-SV-F162B B-TB233-4 and B-TB233-5 m,4AS//9$&
{ } Q BF-SV-F162D B-TB243-4 and B-TB243-5 I h
8b C 6 N ////h I
su BF-SV-F163B B-TB243-10 and B-TB243-11
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1 08 8.4.10
~At panel 10C602 reinstall f es F5B and F68.
Mll(*[ek 8.4.11 Establish communication bet n 10C601/10C602 5
and 10C651 in control room START VCR MONITORING ROD DISPLAY (FULL IN/ FULL OUT I
INDICATION) and the timer.
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8.4.12 INSERT KEYS in 10C601 DIVISION 1 CHANNEL A and B ARI MANUAL INITIATION switch S2A and S2C.
(03 ///Cb 8.4.13 Place the DIV.ISION 1 CHANNEL A MANUAL INITIATION switch SIA to ARMED position and j
depress SIA on 10C651.
Initiate RRCS from DIVISION 1 CHANNEL B MANUAL INITIATION switch SIC by placing in ARMED postion and depressing SIC on 10C651.
Start the timer at the same time SIC is depressed.
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PSSUG-PTP-p a $
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INITIALS /DATE f
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{$$ T 8.4.14 Run VCR for at least 2 minutes after FULL IN indication for all rods is observed, and the HCU accumulators have been reset, then stop.
4S0 J //o/95, 8.4.15 Verify that all control rods begin moving in within 15 seconds of the initiation
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signal. Record the following:
Function Design Actual M.1 4
gip Time to begin all rods (tab (lso(8 6 moving in (seconds) verification 115 '.
1 0 8.4.16 M.0 Verify that a,11 control rods are fully inserted from the fully withdrawn position within 25 seconds of the initiation signal and record the followings j
i Actual Function Design Time to complete all rods full in (seconds) verification 125 k.(
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8.4.17 On 10C651, depress RRCS ARI RESET switches S3A and S3C after the RRCS ARI ready FOR RESET DIVISION 1 CHANNEL A and B status lights come ON.
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8.4.18 On 10C651 depress RRCS RESET switches S4A and i
S4C after the RRCS READY FOR RESET DIVISION 1 CHANNEL A and B status lights come ON.
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8.4.19 Withdraw all control rods to the full-out Il (3 Il(%PL position.
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8.4.20 Establish communication between 10C601, 10C602 and 10C651 in control room.
Start VCR I
MONITORING ROD DISPLAY (FULL IN/ FULL OUT
)
INDICATION) and timer.
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i 8.4.21 Insert keys in 10C602 DIVISION 2 C.H. A & CH. B j
ARI INITIATION switch S2B and S2D.
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SIM8I PAGE NO. 288, R G f. f : - - --~~
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INITIALS /DATE 8.4.22 Place the DIVISION 2 CH A MANUAL INITIATION '
switch SlB to ARMED position and depress SIB i
on 10C651.
Initiate RRCS from DIV. 2 CH. B MANUAL INITIATION switch SlD by placing it in i
the ARMED position and depressing SlD on 10C651.
Start the timer at the same SID is l
depressing.
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8.4.23 Run VCR for at least 2 minutes after FULL IN indication for all rods is observed and the HCU accumulators have been reset, then STOP.
/ OM/D 8.4.24 Verify that all control rods begin moving in with'in 15 seconds of the initiation signal record the following:
i Function
_ Design Actual Time te begin all rods Isc ll t*l84 i
moving in (seconds) verification 115 T 4.s*
f 1
8.4.25 Verify that all control rods are fully inserted from the fully withdrawn position
[0,go within 25 seconds of the initiation signal and record the following I
Function Design Actual i
Time to complete all rods full in (seconds) verification 125 6.(.s (W5 - Ot 8.4.26 On 10C651, depress RRCS ARI RESET switches S3B and S3D after the RRCS ARI. READY FOR RESET
/
/A' h DIVISION 1 CHANNEL A and B status lights come ON.
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6.4.27 On panel 10C651 depress RRCS RESET switches S4B and S4D af ter the RRCS READY FOR RESET DIVISION 2 CHANNEL A and B status lights come ON.
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8.4.28 Restore the CRDHS per the direction of the shift superintendent.
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PSSUG-PTP-SAgg' REV. NO. LK g,ztgai/gf
-7 PAGE NO. 289.
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ATTACHMENT 3 ATTACHED DRAWINGS Drrwing #
Sheet #
Rev. #
Drawing #
Sheet #
Rev. #
E-0004-1 5
762E180 1
15 E03043-0 3
762E180 2
14 E-4009-1 A
13 762E180 3
1 E-4009-1 1 of 18 6
762E180 4
14 E-4009-1 2
5 762E180 5
12 E-4009-1 3
8 762E180 6
14 E-4009-1 4
5 762E180 7
9 E-4009-1 5
5 762E180 8
14 E-4009-1 6
4 762E180 9
14 E-4009-1 7
5 762E180 10 11 E-4009-1 8
4 762E180 11 14 E-4009-1 9
7 762E180 12 9
E-4009-1 10 7
762E180 13 9
E-4009-1 11 6
762E180 14 10 E-4009-1 12 7
762E180 15 17 E-4009-1 13 8
762E180 16 17 E-4009-1 14 8
762E180 17 3
E-4009-1 15 7
762E180 18 4
E-4009-1 16 7
762E180 19 15 E-4009-1 17 3
762E180 20 15 E-4009-1 18 0
791E414AC 1
18 E-6016-0 1 of 2 2
791E414AC 2
5 E-6016-0 2
2 791E414AC 3
16 E-6794-0 1 of 3 1
791E414AC 4
15 E-6794-0 2
2 791E414AC 4A 6
E-6794-0 3
2 791E414AC 5
1 791E414AC 6
9 l
7918414AC 7
9 791E414AC 8
10 791E414AC 8A 7
791E414AC 9
14 791E414AC 10 10 791E414AC 11 13 l
791E414AC 12 8
791E414AC 13 16 791E414AC 14 12 791E414AC 15 9
791E414AC 16 8
791E414AC 17 10 791E414AC 18 11 791E414AC 19 11 791E414AC 20 13 791E414AC 21 8
791E414AC 22 11 l
791E414AC 23 10 791E414AC 24 11 791E414AC 25 9
791E414AC 26 10
ATTACHMENT-3 (cont.)-
ATTACHED DRAWINGS Drrwing #
Sheet #
Rev. #
Drawing #
Sheet #
Rev. #
944E309AC 1
7 944E309AC 29 7
944E309AC 2
4 944E309AC 30 4
944E309AC 3
6 944E309AC 31 6
944E309AC 4
5 944E309AC 32 3
944E309AC 5
5 944E309AC 33 3
944E309AC 6
4 944E309AC 34 3
944E309AC 7
5 944E309AC 35 4
944E309AC 8
4 944E309AC 36 3
944E309AC 9
5 944B309AC 37 3
944E309AC 10 4
944E309AC 38 4
944E309AC 11 5
944E309AC 39 4
944E309AC 12 4
944E309AC 40 3
944E309AC 13 4
944E309AC 41 3
944E309AC 14 4
944E309AC 42 3
944E309AC 15 3
944E309AC 43 3
2 944E309AC 16 3
944E309AC 44 4
944E309AC 17 3
944E309AC 45 3
944E309AC 18 3
944E309AC 46 4
944E309AC 19 3
944E309AC 47 3
944E309AC 20 3
944E309AC 48 3
944E309AC 21 3
944E309AC 49 2
I 944E309AC 22 3
944E309AC 23 3
944E309AC 24 3
944E309AC 25 3
944E309AC 26 3
944E309AC 27 3
944E309AC 28 5
/
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