ML17138B012
| ML17138B012 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 12/11/1979 |
| From: | Parr O Office of Nuclear Reactor Regulation |
| To: | Curtis N PENNSYLVANIA POWER & LIGHT CO. |
| References | |
| NUDOCS 7912280597 | |
| Download: ML17138B012 (8) | |
Text
DISTRIBUTION:
DEg 14. 1979 Docket Nos.:
50-387/388 Hr. Norman W. Curtis Vice President Engineering and Construction Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101
Dear Hr. Curtis:
ELD IE (3)
Docket Files NRC PDR Local PDR LWR ¹3 File DVassallo DRoss SVar ga FWilliams OParr SHiner MRushbrook (w
RMattson SHanauer JKnight RTedesco RDeYoung VMoore HErnst RDenise bcc:
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SUBJECT:
SUSQUEHANNA STEAM ELECTRIC STATION, UNITS NOS.
1 AND 2-REQUEST FOR ADDITIONAL INFORMATION As a result of our review of your application for operating licenses for the Susquehanna Steam Electric. Plant, we find that we need additional informa-tion in the area of Instrumentation and Control Systems.
The specific information required is listed in the Enclosure.
Some of this review has been performed by the Savannah River Plant (SRP).
The questions in the Enclosure were originated by SRP.
Please contact us ifyou desire any discussion or clar ification of the information requested; Sincerely.
Origl2101 SianBIl bp,'laII Parr 01 an D. Parr, Chi ef Light Water Reactors, Branch No.
3 Division of Pro)ect Management
Enclosure:
As Stated cc:
See Next Page OFFICE SURNAME R I3 SHiner ec DPM. LW ) ¹3 ODParr 12/ I'f /79 12/ /f /79 OATE$
JVRC FORM 318.(9 76) NRCM 0240
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Mr.. Norman W. Curt i s cc:
Mr. Earle M. Mead Project Engineering Manager Pennsylvania I'ower 8 Light Company
- 2. North Ninth Street Al l.entown, Pennsyl vania 18101 I
Jay'ilberg, F,:sq.
Shaw,,Pittman, Potts Trowbridge
. 1800 M Street, N.
W.
D. C.
20036 Mr. William E. Barberich, Nuclear Licensing Group Supervisor Pennsylvania Power 8 Light Company 2 North Ninth Street Al 1 ento',
Pennsyl vania 18101 Edward M. Nagel, Lsqu'ire General Counsel and Secretary Pennsylvania Power 8 Light Company 2 North Ninth Street.
Allentown, Pen!!sylvani'a 1810'l Bryan Snapp, Esq.
Pennsylvania Power
& Light, Coo!pany 901 Hamilton Street All.entown, Pennsyl vani a 18101
~Robert M. Gallo Resident Inspector P. 0.
Box 52 Shickshinny, Pennsylvania 18655 Susquehanna Environmental Advocates c/o Gerald Schultz, Esq.
500 South River Street Wilkes-Barre, PA 18702 John'L.
Anderson Oak Ridge National Laboratory
.Union Carbide Corporation Bldg. 3500, P. 0.
Box X
Oak Ridge, Tennessee 37830 I
1 1r. Robert J.,
Sh ov 1 in Project Manager Pennsylvania Power and Light Co
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2 North Ninth Street Al 1 entown, Pennsyl vania 18101 l1atias F. Travieso-Diaz, Esq.'haw, Pittman, Potts 8
Trowbridge 1800 M Street',
N.
W; Washington, D. C.
20036 Dr. Judith H. Johnsrud Co-.Director E n v i i onmenta 1
Co a 1 it i on on
'uclear Power
'33 Orl ando Avenue
,State College, PA 16801 Mr. Thomas M. Gerusky, Director
'ureau of Radiation Protection Department of Environmental Resou! ces Common> ealth of Pennsylvania P. 0.
Box 2063 Harrisbu! g, PA 17120 Ms. Colleen Marsh Box 538A; RDii4 Mountain Top, PA 18707 11rs. Irene 'Lemanowicz, Chairperson The Citizens Against Nuclear Dangers P. 0.
Box 377 ROii 1
- Berwick, PA 18503
ENCLOSURE 032.50 (3.12)
(7.1.2.5.8)
(7.1.2.6.16)
Regulatory Guide 1.75 and IEEE Standard 384-1974 on Criteria for Separation of Class IE Equipment and Cir-cuits do not apply to SSES because they were issued after the CP.
Separations criteria for safety related mechanical and electrical equipment are described in 3.12.
Specific exceptions to RG 1.75 are identified in 3.13 for non-NSSS equipment, but no similar list is supplied for NSSS equipment.
A brief, general discussion is contained in 7.1.2.5.8.
Identify all specific exceptions to RG 1.75 and IEEE 384-1977 for NSSS equipment and justify each.
~ < f H
P 032.51 (7.2.1'.1.4.2)
(Table.7.6-5)
Discussion of the APRM system on page 7.2-5 indicates the maximum setpoint is 125K reactor power.
Table 7.6-5 lists the nominal APRH setpoint as 120% and the range as 2X of full scale.
This setpoint is significant for the accident analysis in 15.0.
Discussion of the APRN system on page 7.2-5 indicates the maximum setpoint is 125% reactor power, but table 7.6-5 lists the nominal setpoint as 120% with a, range of 25 of full scale.
Clarify this discrepancy and identify the maximum setpoint for accident analysis.
0
032.52 (Table 7.2-4)
(7.2.1.2.2)
(7,C,t,Z,S,)
(7.Z,1,2,6}'able 7.2-4, Design Basis Setpoints, was deleted in Revision ll.
Several sections still refer to data con-tained in that table.
Several references are made to design basis setpoints previously listed in Table 7.2-4.
This table has been intentionally left blank.
Please clarify this discrepancy.
032.53, (7.2.2.1.2.4.4)
(Table 7.2-5)
Section 7.2.1.1.4.8 (Testability) states, "During preoperational testing the sensors are tested using an accepted industry method and actual response time data are compared to design requirements for acceptance".
Section 7.2.2.1.4.4 (BTP 24) states in part that the sensor response time test method has not been resolved for neutron monitoring system (APRN and IRN) and main steamline radiation monitoring trip points.
question 032.32 asks for a description of the Startrek computer system which is used for startup testing.
The question also asks for separation criteria for permanent and temporary wire as well as specifications of qualification testing of electrical isolators.
This question, directed at 7.3 only, has not been answered.
The discussion of compliance with BTP 24 is incomplete.
Describe methods to be used to perform periodic response time tests of RPS system to verify design specifications are met.
Identify all specific exceptions to RG 1.118
and IEEE 338-1977.
Describe separation criteria for permanent and temporary wiring and describe the qualification tests for electrical insulators.
V 1