ML19254F456
| ML19254F456 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 11/05/1979 |
| From: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7911090465 | |
| Download: ML19254F456 (34) | |
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PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 SHIELDS L. D ALTROFF susc'im'ic"enoEsom November 5, 1979 Re: Docket N os. : 50-277 50-278 Mr. Thomas A.
Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors United States Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Ippolito:
This is in res p ons e to your request of October 5, 1979 f or additional inf ormation pertaining to our application for amendments to Facility Operating License Nos. DPR-44 and DPR-56 for the Peach Bottom Atomic Power Station Unit Nos. 2 and 3 submitted on October 27, 1979.
The proposed amendments involve the use of analog transmitter / trip unit systems for certain engineered saf eguard sens ors.
Your reques ts are restated below with ou r responses.
1.
Provide the interface inf ormation specified in the GE Topical Report NEDO-21617-A for each of the f our parameters specified in your application for amendment.
Resconse The response co item 1 is contained in Appendix A (attached).
2.
For each location, state the maximum and minimum abnormal environmental conditions that are expected during normal, accident, and p os t-(
accident situations.
The information should,
include both magnitude and duration.
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7911090
Mr>
T. A.
Ippolito, Chief Page 2
Response
Environmental p rofiles oeing developed f or our response to Bulletin 79-01 will als o be used in responding to this item.
It is anticipated that we will be able to.f orward this information t o y ou by January 30, 1980.
3.
For each parameter, state the position of the trip output logic select switch in terms of the opening or closing of the trip output contacts on a loss of p ow e r.
Response
Trip unit switch positions are defined as follows:
Normal - signal greater *than the trip point causes trip output of 24VDC Reverse - signal greater than the trip point causes trip output of zero volts - DC Contact p os iti on Instrument Switch Position on Loss of Power PIS 5-12A,B,C,D Reverse Open PISH 2-3-55A,B,C,D Note 1 Note 1 PSL 2-3-55A,B,C,D Reverse Open PISL 2-3-52A,B,C,D Reverse Open PSLL 2-3-52A,B,C,D Reverse Open LISH 2-3-72A,B Note 2 Note 2 PISHH 10-100A,B,C,D Normal Open PSH
.'. 0- 10 0 A, B, C, D Normal Open Note 1:
These trip units are existing plant equipment.
Since output to a slave trip unit is only a portion of trip unit used f or this modification, switch position is not applicable.
Note 2:
These trip units are existing plant equipment.
Since analog output is only portion of trip unit used f or this codification, switch position is not applicable.
Very truly yours,
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Attachment
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b Philadelphia Electric Co.
Dockets 50-277 & 50-278 November, 1979 APPENDIX A-NEDO 21617-A 5.4.1 Specific Instrument Loops (1)
(2)
(3)
(4)
(5)
Variable Part # of New System Engineered Vendor Model Name device Instrument Involved Safeguard of transmitter replaced Loop Division Drywell PSS-12
-A PIS-12
-A RPS Scram IA Rosemount Pressure
-B
-B Sensor IB Model #
-C PISS-12
-C IIA 1151GP
-D
-D IIB Reactor PS2-3-51
-A
- PT2-3-5
-A RPS Con-IA Rosemount Pressure
-B
- PISir2-3-55
-B denser Low IB Model #
Vacuum and IIA IISIGP
-C
- PSL2-3-55
-C HSIV IIB
-D
-D closure bypass Reactor PS2-3-52 -A PT2-3-52
-A Core Spray, I
Rosemount Prescure
-C PISL-2-3-52 -C RilR, Recire.
I Model #
-B
-b Permissive II IISIGP
-D PSLL2-3-52
-D II a
Reactor LITS 2-3-59-A
- LT2-3-72 &
-A Nuclear Non Safe Rosemount Water
-b
- LISil2-3-72
-B Boiler guard Model #
'N Level 1151DP T. I 2 8 5
-A LI2-3-85
-A
-B
-B NO 4*
LI2-3-85
-Ax LI2-3-85
-Ax
-Bx
-Bx
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Philadelphia Electri c Co.
Dockets 50-277 & 50-278 November, 1979 APPENDIX A - NEDO 21617-A 5.4.1 Specific Instrument Loops (1)
(2)
(3)
(4)
(5)
Variable Part # of New System Engineered Vendor Model Name device Instrument Tnvolved Safeguard of transmitter replaced Loop Division Drywell PS10-100
-A PT10-100
-A ADS initia-I Rosemount Pressure PS10-101 eC PISilll10-100 -C tion, II P I C,
I M7 del i
-d
-B Core Spray II liSIGP PS10-119 W
P Sil 10-100
-D
& diesel-II generator initiation, containment spray permissive
- Existing plant equipment
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Philadelphia Electric Co.
Docket Nos. 50-277 & 50-278 N ove mb e r, 1979
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i Appendix A (Cont'd) 6 5 4.2 Trip Unit Cabinet 1)
F or cabinet lay ou t see the f ollowing prints:
r 6280-M-1-EE-380 Arrangement of Equipment panel 2AC65D (typical f or panels 3AC65D and 3BC65D)
T'g list for panels 6280-M-1-EE-382 a
6280-M-1-EE-383 Equipment Identity 6280-M-1-EE-386 Card File Tag List 2)
Division to which cabinet is assigned:
I Cabinets 2AC65D & 3AC65D are f or RPS Division IA and IB and ECCS Division I.
Cabinets 2BC65D & 3BC65D are f or RPS Division 3
IIA and IIB and ECCS Division II.
i 3)
See the following Elementary Diagrams for the trip variables of each card slot:
6280-M-1-S-54, she. 19 Reactor Protection System 6280-M-1-S-65, Shes. 22 & 23 Residual Heat Removal 5 4.3 Environmental Interface 5.4.3 1 Environmental profiles are being developed f or Peach Bottom Reactor enclosure c omp ar t ment s required for IE Bulletin 79-01.
The profiles will be used to determine normal operation and p os t-accident temperature and humidity conditions for areas where the retrofit hardware will be located.
It is anticipated that we will be able to f orward the required inf ormation to you by J anu a ry 30, 1980.
5.4.3.2 The seismic qualification requirements are defined in the specification f or the panel and includes the response spectrum curves for the location in which the panels are to be located.
All panels supplied f or this s t ructural configuration; modification utilize the same they differ only in the c omp le me n t of panel mounted 7
196
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Philadelphia Electric Co.
Docket Nos. 50-277 & 50-278 November, 1979 Appendix A (C ont 'd )
a devices.
The seismic qualification was perf ormed by the use of a mathematical model of the panel loaded 4
with a fc11 set of c omp onen t s including the mounting of components in spaces originally designated for spares.
Design seismic stresses were compared against 60% of the material yield stress and maximum credible seismic stresses were compared against 90% of the material yield stress.
In all cases, the computed stresses are well within the acceptance criteria.
In addition, the peak acceleration input to the components mounted on the panels are well within the limits to which the individual components vert tasted.
5.4.3 3 The trip unit cabinets are located (as shown in Figure 5-3 of NEDO-21617-A) near the instrumentarion racks.
The lack of space in the cable spreading room and the control room is the p rimary reason for choosing this location.
The equipment in the t2ip unit cabinets is qualified to the requirement of the ?sach Bottom FSAR.
This Ic. cation will be re-evaluated to dctermine its acceptability for the environmental p rofiles addressed in 5.4.3.1.
5.4.4 Specific Plant Interconnections See the fo=11owing prints for interconnection diagrams which show the interconnections between extsting logic cabinets and instrument cabineta, and the new trip unit cabinets:
6280-M-1-S-42, sh 1,2 RCIC System 6280-M-1-S-54, sh 1,7,8, 11,19 RGactor Protection System 6280-M-1-S-65, sh 1,3,4, Elem. Diag.
5,6,7,8 RHR System 9,10,11 22,23 Panels 25-5, 25-6, 25-5-2, 25-6-2, 25-51, 25-52 are near the instrumentation racks Panel COSA is in the control room Panel C43 is close to the control
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Philadelphia Electric Co.
Docket Nos. 50-277 & 50-278 Noverber, 1979 Appendix A (C ont 'd )
room and used f or backup control 5.4 5 Field Calibration Rack A " Field Calibration Rack" is not required for this modification.
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