ML18031A348
| ML18031A348 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 01/16/1980 |
| From: | Parr O Office of Nuclear Reactor Regulation |
| To: | Curtis N PENNSYLVANIA POWER & LIGHT CO. |
| References | |
| NUDOCS 8001310368 | |
| Download: ML18031A348 (15) | |
Text
I'll(IINlIl'ISFit,f II'i stri.bution encl:
Doc et Filesu D.
NRC PDR D.
Local PDR S.
LWR 83 Fi1 e F.
0.
Docket Hos.
50-387 388 Ross Vassallo Varga Williams Parr SMiner M. Rushbrook R. Mattson S.
Hanauer J.
Knight OELD R
Tedesco R.
DeYoung V. Moore W. Kreger Ernst R. Denise IE (3)
Mr. Norman W. Curtis JAtk 16 1980 Yfce President - Engfneerfng
- and 'Construction Pennsylvanfa Power and Light Company
- 2. North Ninth Street Allentown, Pennsylvania 18101
Dear Mr. Curtis:
BCC:
SUBJECT:
SUSQUEHANNA STEAM ELECTRIC STATION, UNIT NOS.
1 AND 2-REQUEST FOR ADDITIOHAL 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 information in the area of Effluent Treatments Systems.
The specific information required is listed fn the Enclosure.
Please contact us ff you desire any discussion.or clarification of the information requested.
Sincerely, Orfptn".t 6@nag bg Q. D.,Para...,.."-"
Olan D. Parr, Chief Light Water Reactors Branch INo.
3 Division of Project Management
Enclosure:
As Stated cc w/enclosure:
See next page
$ nb/5(os<
9'FFICE SURNAME OATE P, pg7.
LPM SMineriLLM 1/ /ro /80 LM+3pBC ODParr 1/yt', /80 NRC FORM 318 {9 76'I NRCi".I 0240
~ U.S. GOVERNMENT PRINTING OFFICE: 1979 289.389
I s
Hr. Norman W. Curtis JAN 1 6 J980 cc:
Hr. Earle M. Head
'Project Engineering Manager Pennsylvania Power
& Light Company 2 North Ninth Street Al 1 entown, Pennsyl vani a 18101 Jay Silberg, Esq.
Shaw, Pittman, Potts.&
Trowbridge 1800 M Street, N.
W.
Washington, D. C.
20036 Mr. William E, Barberich, Nuclear Licensirrg Group Supervisor Pennsyl vani a Po>er
& Light Company 2 North Ninth Street Al 1entovrn, Pennsyl vania 18101 Edward M. Nagel, Esquire General Counsel and Secretary Pennsylvania Power
& Light Company 2 North Ninth Str.eet Al 1 entown, Pennsyl vani a 18101 Bryan Snapp, Esq.
Pennsylvania Po~r
& Light Company 901 Hamilton Street Al 1 entown, Pennsyl vania 18101 Robert M.-Gallo Resident Inspector'.
0.
Box S2 Shickshinny, Pennsyl vani a 18655 Susquehanna Environmental Advocates c/o Gerald Schultz, Esq.
500 South River Street Wi lkes-Barre, PA 18702 John L. Anderson Oak Ridge National Laboratory Union Carbide Corpoi ation Bldg. 3500, P. 0.
Box X
Oak Ridge, Tennessee 37830 Hr. Robert J. Shovlin Project Manager Pennsylvania Pol e r and Light Cr~.
2 North Ninth Street Al 1 ento<vTi, Pennsyl vania 18101 Matias F. Travieso-Diaz, Esq.
Shaw, Pittman, Potts Trowbridge 1800 M Street, N.
W.
Washington, D. C.
20036 Dr. Judith H. Johnsrud Co-Director Env'-onmental Coalition on Nuclear Power 433 Orlando Avenue State College, PA 16801 hr. Thomas H. Gerusky, Director.
Bureau of Radiation Protection Department of Environmental Resources Commonwealth of Pennsylvania P. 0.
Box 2063 Harrisburg, PA 17120 Hs. Colleen Marsh Box S38A, RD84 Mountain Top, PA 18707 ftrs. Irene Lemanowicz, Chairperson The Citizens Against Nuclear Dangers P. 0.
Box 377 ROf/1
- Perwick, PA 18503
EFFLUEINT TREATNEI')T SYSTEMS BRANCH SUS UEHANNA STEAl1 ELECTRIC STATION UNIT NOS.
1 AND 2 DOCKET NOS. 50-387 388 SECOND ROUND RE UEST 321. 7 Your response to question 321.6, items 1-4, on the Process Control Program (PCP) for Solidification is not acceptable, since the United Nuclear Industries (UNI) topical report has not been reviewed and approved by NRC staff as an acceptable reference.
You should-submit a
PCP.
The PCP may be extracted from or based on information contained in the draft UNI topical report.
Your response to item 5 is acceptable.
OFFICE )
SURNAME DATEJt NRC FORM 318 (9 76) NRCM 0240
~U.S. GOVERNMENT PRINTING OFFICE: 1979'289 369
'i
~
1'
Dgi"
~ ~970 Docket Nos.:
50-387/38&
Mr. Norman M. Curtis Vice President Engineering and Construction Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101
Dear Mr. Curtis:
DISTRIBUTION:
Docket Files NRC POR Local POR LMR 43 File DVassallo ORoss SVarga FMilliams OParr SMiner MRushbrook (w/r RMattson SHanauer JKnight RTedesco ROeYoung VMoore MErnst RDenise ELD IE (3) bcc:
NSIC TIC TERA ACRS (16) extra copies)
SUBJECT:
SUS(UEHANNA STEAM ELECTRIC STATION, UNITS NOS.
1 ANO 2>>
RE/VEST 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 if you desire any discussion or clarification of the information requested.
Sincerely, Ori,-'".~'"""6bp'
~il ALT a)~
Gian 0. Parr, Chief Light Mater Reactors, Branch No.
3 Division of Prospect Management
Enclosure:
As Stated cc:
See Next Page OFFICE SURNAINE OaTE g:
R~I3 SMiner ec OPM LM g3 ODParr 12/ /f /79 NRC FORM Slb.(9 N) NRCQ 02%1
~
~
. *US. GOVERNMENTPRINTING OFFICE 1979489-199"
Mr., Norman W. Curtis cc:
tir. Earle M. tread Project Engineering Manager Pennsylvania Power
& Light Company 2, North Ninth Street Al l.entown, Pennsyl vania 18101 Jay'i1 berg, Esq.
Shaw, Pittman, Potts Trowbridge 1800 M Street,.
N.
W.
D. C.
20036 Mr. William E.
Ba! berich, Nuclear Licensing Group Supervisor Pennsylvania Power
& Light Company 2 North Ninth Street Al 1 ento',
Pennsyl vania 18101 Edward M. Nagel, Lsquire General Counsel and Secretary Pennsylvania Power
& Light Company 2 North Ninth Street Al 1 entown, Pennsyl vani'a 18101 Bryan Snapp, Esq.
Pennsylvania Power 8 Light Company 901 Hamilton Street Al l.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 Corporatinn Bldg. 3500, P. 0.
Box X Oak Ridge, Tennessee 37830 fir. Robert J.
Shovl in Project Manager Pennsylvania Power and Ligh' North Ninth Street Al 1 entoil, Pennsy'I vania 1810 i Matias F. Travieso-Diaz, Esq.
Shaw, Pittman, Potts Trowbridge 1800 M Street; N.
Washington, D. C.
20036 Dr. Judith H. Johnsrud Co-Director Environmental Coalition on l"uclear Power 433 Orlando Avenue State College, PA 16801 Mr. Thomas M. Gerusky, Di recto!
Bureau of Radiation Protection Department of Environmental Resources Con!mon>saith of Pennsylvani<s P. 0.
Box 2063 Ha rrisburg, PA 17 120
- f is. Colleen Marsh Box 538A, RDP4 Mounta in Top, PA 18707 Mrs. Irene Lemanowicz, Chairperson The Citizens Against Nuclear Dangers P. 0.
Box 377 ROD 1
- Berwick, PA 18503
h
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'ecause they weve issued after the CP.
Separations criteria fov safety related mechanical and electrical equipment are described in 3.74.
.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.
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
'.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 2X 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)
(7.2.~,Z.5)
(7.2.1.2-.6)
Table 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 (APRM and IRM) and main steamline radiation monitoring trip points.
guestion 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
0 and IEEE 338-1977.
Describe separation criteria for permanent and temporary wiring and describe the qualification tests for electrical insulators.