ML18086B447
| ML18086B447 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/16/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Uderitz R Public Service Enterprise Group |
| References | |
| NUDOCS 8204290482 | |
| Download: ML18086B447 (5) | |
Text
APR 1 s i9BZ Docket No. 50-311 DISTRIBUTION ~
Docket File NRC PDR Local PDR ORB l File D. Eisen hut OELD OI&E (1)
W. Ross Mr. Richard A. Uderitz, Vice President -
J. Heltemes Nuclear
- Public Service Electric and Gas Company Mai l Gode Tl 5A P. 0. Box 570 Newark, New Jersey 07101
Dear Mr. Uderitz:
On November 20, 1981, Public Service Electric and Gas Company submitted a document to NRG describing the Reactor Protection System/Engineered Safety Features Actuation System Setpoint Methodology for Salem Unit 2.
In order for the staff to complete the review of this document, particularly Table 3-4, I request that you provide, within 30 days of receipt of this letter, responses to the items in the enclosure to this letter.
Enclosure:
Request for Additional Information cc w/enclosure:
See next page
- .J Sincerely,
\\5\\
Steven A. Varga, Chief Operating Reactors Branch No. 1 Division bf Licensing
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NRG FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY USGPO: 1981-335-960
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Mr. J. A. Jones Carolina Power and Light c*ompany cc:
G. F. Trowbridge, Esquire Shaw, P*ittman, Potts and Trowbridge 1800 M Street, N.W.
Washington, D. C.
20036 Hartsville Memorial Library.
Home and Fifth Avenues Hartsville, So~th Carolina 29550 U. s. Nuclear Regulatory Commission Resident Inspector's Office H. B. Robinson Steam Electric Plant Route 5, Box 266-lA Hartsville, South Carolina 29550 Alan S. -Rosenthal, Chairman
_Atomi_c Safety.and Licensing Appeal Board Panel U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Richard S. Salzman Atomic Safety and Licensing Appeal Board Panel U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Dr. w. Reed J*ohnson Atomic Safety and Licensing Appeal Board Panel U. s. Nuclear Regulatory Commission Washington, D. C.
20555 James P. O'Reilly*
Regional Administrator - Region II U. S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303
I
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ENCLOSURE 9, *.
-REQUEST FOR ADDITIONAL INFORMATION SALEM NUCLEAR GENERATING STATION - UNIT 2 RPS/ESFAS SETPOINT METHODOLOGY
- 1. Being ~hat th~ sensor drift for~the Rosemount sensors-was assumed to be*+.25% for a six month period, justify taking credit for a sensor drift of. 5% for th~ following protectfon-, channels:
Pressurizer Pressure - Low Reactor Trip Pressurizer Pressure High Pressurizer Pressure - Low Safety Injection
- ._Differential Pressure Between Two Steamlines - High Steam F1ow in Two Steamline - Migh
. Steamline Pressure - Low
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2~ What is the justification for_ those rack drift allowances that are less than 1%, specifically steam flow in two steamlines?
- 3.
~rovide the reason why an environmental allowance is not provided for Steam Generator Water Leve-1 Low if one is provided for th_e Low-Low protection channel.
- 4.
Provjde justification for no channel uncertainties for the Undervoltage RCP and Underfrequency RCP channels.
- 5.
Con~erning Pressurizer Pressure - Low Safety Injection, why isn't an environmental allowance included for the event of a slow steamline break that raises the containment pressure?
II
. 6.
Regarding the Undervoltage - Reactor Coolant Pumps protectton channels:
a)
What is the bus voltage?
b)
Ar_e the values in Table 3-4 for the Safety Analysis Limits Allowable Value and Trip Setpo_iri~ correct? If so, jus_tify these values particularly the Safety Analysis Limit being between the Allowable Value and the Trip Setpoint. Also, if these values are correct, justify the Total *Allowance.
If.the value~ are in~orfect, provide co~rect values.
- 7.
What-is the instrument span for Differential Pressure*Between-Twe Steamlines?
- 8.
Provide the bases for establishing the trip setpoints for the following
- channels (excluding those channels for which the Safety Analysis Limit**
is prbvided through response of Question 9).
Power Range, Neutron Flux - High Positive Rate Power R!lnge, Neutron Flux - High Negative *Rate Inte~mediate Range, Neutron Flux Source Bange, Neutron Flux Overpower tiT Steam/Feedwater Fl ow Mismatch Differential Pressure Between Two Steamlines High Steam Flow in Two Steamlines - High
_Tavg - Low-Low Pressurizer Water Level - High_
I 4) *
.,. r~.,;_ '
. 9.
For the following events:
Boron Dilution Event Turbine Trip Loss of Offsite Power to the Station Auxilfaries (Station Blackout)*
Accidental.Depressurization of: the fv1a_i_n_ Steam System.
Major Secondary-System Pipe Ruptures. * --
What protection channels are taken primaf-y credit for in the safety*
analysis in any manner.
If credit is -taken for any channe*l. for which the Safety Analysis Limit has not been supplied in Table 3-4 of the previous submittal~ supply the limit for that channel.
9b. Chapter 14 of the Salem _FSAR takes credit for Power Range, Neutron Flux - High Negative Rate reactor trip for Rod Cluster Control Assembly Misalignment.
Provide the Safety Analysis Limit for this channel.
- 10.
The Trip Setpoint and the Allowable. Val_ue for Steam Generator Water Level - Low Low-differ from what is currently in the Salem Unit 2 Technical Specifications.
A~e you proposing a chan9e to the Technical Specifications or are the.values in Tab~e 3-4 incorrect?