ML20209D880
| ML20209D880 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Diablo Canyon |
| Issue date: | 10/31/1984 |
| From: | Udy A EG&G, INC. |
| To: | NRC |
| Shared Package | |
| ML082410749 | List:
|
| References | |
| CON-FIN-A-6493, FOIA-86-197, RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 GL-82-33, NUDOCS 8502070461 | |
| Download: ML20209D880 (14) | |
Text
_-..
- - - - - = = - - - - - - - - - - - - - - - -
9 CONFORMANCE TO REGULATORY GUIDE 1.97 DIABLO CANYON NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 A. C. Udy Published October 1984 EG&G Idaho, Inc..
Idaho Falls, Idaho 83415 Prepared for the U.S. Nuclear Regulatory Comission Washington, D.C.
20555 Under DOE Contract No. DE-AC07-76ID01570 FIN No. A6493 I
l W*'*]6%I-vk }
CONTENTS 1
ABSTRACT.....................................'.........................
11 FOREWORD..............................................................
11 1.
INTRODUCTION.....................................................
1 2.
REVIEW REQUIREMENTS..............................................
2 3.
EVALUATION.......................................................
4 3.1 Adherence to Regulatory Guide 1.97.........................
4 3.2 Type A Variables...........................................
4 3.3 Exceptions to Regulatory Guide 1.97........................
5 4.
CONCLUSIONS......................................................
9 5.
REFERENCES.......................................................
10
+
e i
l l
111 9
e me--,-
~
.m, y---
g g
-3
....=
CONFORMANCE TO REGULATORY GUIDE 1.97 DIABLO CANYON NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 1.
INTRODUCTION On December 17, 1982, Generic Letter No. 82-33 (Reference 1) was issued by D. G. Eisenhut, Director of the Division of Licensing, Nuclear Reactor Regulation, to all licensees of operating reactors, applicants for operating licenses and holders of construction permits. 'This letter
~
~
included addittenal clarification regarding Regulatory Guide 1.97, Revision 2 (Reference 2) relating to the requirements for emergency response capability. These requirements have been published as Supplement 1 to NUREG-0737, "TMI Action Plan Requirements" (Reference 3).
The Pacific Gas and Electric Company, the Itcensee for the Diablo Canyon station, provided a response to the generic letter on April 18, 1983 (Reference 4). The letter provided a schedule for the submittal of additional information. By letters dated September 9, 1983 (Reference 5),
j and September 4,1984 (Reference 6), the licensee provided additional information on conformance to Regulatory Guide.1.97, Revision 3 (Reference 7).
~
{
This report provides an evaluation of these submittals.
l i
I i
1
.. - - + -
. _... =.
._e % w.
m
~-w w
i-.-
-,-rg sv--y
---9--.w m-
r
---+--
--e+-'+-
>wv-M N
...g..
the provisions of the guide it was noted that no further staff review would be necessary. Therefore, this report only addresses exceptions to the guidance of Regulatory Guide 1.97. The following evaluation is an audit of the licensee's submittals based on the review policy described in the NRC regional meetings.
1 a
i f
i i
1 e
3
., - -.. -.. _ - - - -. - -.. ~ _..
6.
Core exit temperature j
7.
Refueling water storage tank level 8.
Containment sump water level-wide range All the above instrumentation meets or will comply with the Category 1 recommendations of Regulatory Guide 1.97.
3.3 Exceptions to Regulatory Guide 1.97 The licensee identified the following exceptions to the requirements of Regulatory Guide 1.97.
3.3.1 Reactor Coolant System (RCS) Soluble Boron Concentration i
The range of the instrumentation supplied by the licensee for this variable is 0 to 5000 parts per million. The range recommended in the regulatory guide is 0 to 6000 parts per million. The licensee's justification for this deviation from the recommended range is that the boron concentration monitoring system is s'uppl.ied RCS water via the letdown system, which is isolated for most accidents. {With isolation, the post-accident sampling system is used, which does meet the~ recommended range.
We find that this combination of instrumentation is acceptable in complying with the reccmmendations for this variable.
3.3.2 Effluent Radioactivity--Noble Gas Effluent from Condenser Air l
Removal System Exhaust The range of the ir:strumentation supplied by the licensee for this
-4 variable is 10 to 3 uCt/cc. The range recommended by the regulatory
-6
-2
-6 5
guide is 10 to 10 pct /cc (Type C) and 10 to 10 vC1/cc (Type E). This deviation from the recommended range f.s justified by the 5
e' c.---
e w--
~--e.
,--g+-wwm
- ---mee-
==
==
ww
The licensee has shown, by analysis, that should the component cooling water temperature be 45'F, the lowest recorded, sea water temperature (the
~
ultimate heat sink) that the residual heat removal heat exchanger outlet temperature would still be greater than 50'F.
Based on the licensee's analysis, we find the range of 50 to 400*F, which has been supplied for this variable, acceptable.
3.3.5 Accumulator Tank Pressure The licensee has supplied instrumentation for this variable that has a maximum range of 700 psig rather than 750 psig as specified in Regulatory Guide 1.97.
The licensee indicates that the pressure in the accumulators is limited to 700 psig by relief valves. The pressure is manually controlled to within technical specification limits and no accident 1
conditions will cause the pressure to increase. Therefore the licensee's range of 0-700 psig is an acceptable deviation.
3.3.6 Pressurizer Heater Status
'The licensee has supplied instrumentation for this variable that indicates 0 to 600 kilowatts rather than plant specific current as specified in the regulatory guide. The kilowatts of power into the pressurizer heaters is a direct relation to the heater current and voltage.
Based on our technical review and judgment, we find the deviation of measuring pressurizer heater input power rather than current acceptable since the heater power has a known relation to the heater current.
3.3.7 Steam Generator Pressure x
Regulatory Guidd 1.97 recommends instrumentation for this variable with a range from 0 psig to 20 percent above the lowest safety valve setting. The lowest safety valve setting is at 1065 psig; therefore, the recommended range is 0 to 1278 psig. The licensee's instrumentation has a range of 0 to 1200 psig.
7 s
y
,-,.r.
-i 4.
CONCLUSIONS i
Based on our review, we find that the licensee either conforms to or is justified in deviating from the guidance of Regulatory Guide 1.97.
The licensee has committed to submit a schedule for Unit No. 2 instrumentation modifications. Currently, this will be submitted by November 26, 1984 (before fuel loading of Unit No. 2).
5 9
4 k
+
4 9
--+4-
--n-
-e m
-,m,
~
va -
a..
uro..
.... oar u..-
., r,oc.
c 124ss 72%1'-
818UOGRAPHIC DATA SHEET EGG-EA-6651 u.
r.ver,o r....
3 Laiv..L.s.a 3 firk...e. SW.rerLa Conformance to Regulatory Guide 1.97, Diablo Canyon Nuclear Power Plant, Unit Nos. 1 & 2
...r r co L r.o l
v.
r.
October 1984 a.or o.m
& o.rt.
Y is.u.o a.o r v.
A. C. Udy October 1984 i,.oacrer -
. u 1 --.
,n.o o.a.a.r.o.
.v
.oo.
e.c a ni.o.
v u EGaG Idaho, Inc.
Idaho Falls, ID 83415 ii.r m o
..,o.1 o.
o.o..a.r.o
.u
,. c Division of Systems Integration Technical Evaluation Report Office of Nuclear Reactor Regulation m u co co....o r U.S. Nuclear Regulatory Comission Washington, DC 20555 II SUPPLIES.a.r..v orts 13..sgr.Crim m. steer W This EG&G Idaho, Inc. report reviews the submittals for the Diablo Canyon Nuclear Power Plant, Unit Nos.1 and 2, and identifies areas of conformance to Regulatory Guide 1.97, Revision 3.
Any exceptions to these guidelines are evaluated.
1 1
is.v.
i ev is poco..a., a.astsas e a..wo.os o.sca.orous Liuited Distribution
- i. acv.ir,c6 u..c.rio.
ITe. eepe.
Unciassified
.,c......
o,....e. o v..
. r..
Unclassified i, u.. o..ao u i.
.c.
m---
m 9-%,
,y- - - - -
.m
--+---w--y n-