W3P84-1353, Forwards Clarifications to FSAR Chapter 14 Re Startup Test Program.Understands Clarifications Acceptable to NRC
| ML20091A533 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 05/23/1984 |
| From: | Cook K LOUISIANA POWER & LIGHT CO. |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| W3P84-1353, NUDOCS 8405300001 | |
| Download: ML20091A533 (6) | |
Text
_
LOUISIANA 242 ouAnoNoe SrnEer POWER & LIGHT P O BOX G008
- NEW OHLEANS. LOUISIANA 70174 * (504) 366-2345 UIluTIES SYSTEM May 23, 1984 W3P84-1353 Q-3-A29.14 Director of Nuclear Reactor Regulation l
Attention:
Mr. G.W. Knighton, Chief I
Licensing Branch No. 3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
SUBJECT:
Waterford 3 SES Docket No. 50-382 FSAR Chapter 14
Dear Sir:
During recent discussions on the startup test program with the NRC (D. Beker), it was determinec that certain clarifications to FSAR Chapter 14 were in order. We understand that the attached clarifications are acceptable to the NRC.
Yours very truly, K.W. Cook Nuclear Support & Licensing Manage.r KWC/RMF/pco Attachment cc:
E.L. Blake, W.M. Stevenson, J.T. Collins, D.M. Crutchfield, J. Wilson, G.L. Constable, R. Gruel (BNWI) l 8405300001 840023 g'/pk A
PDR ADOCK 05000382 A
\\
i
m ATTACHMENT 1 (1) The response to NRC question 640.7 should be supplemented by the following systems on which testing will not be completed prior to fuel load.
(a) Waste Management System (FSAR 14'.2.12.2.45) - preoperational testing of the containment sump pumps will not be completed until 5% power.
(b) Feedwater System (FSAR 14.2.12.2.66) - preoperational flow testing will be completed during power ascension.
(c) Main Steam System and Steam Generators (FSAR 14.2.12.2.69) -
preoperational testing will be completed prior to 5% power.
(d) Steam Generator Blowdown (FSAR 14.2.12.2.70) - preoperational testing will be completed prior to 5% power.
(e) Extraction Steam System (FSAR 14.2.12.2.71) - preoperational testing will be concluded during power ascension.
(f) Heater Drains and Vents (FSAR 14.2.12.2.72) - preoperational testing will be completed during power ascension.
(g) Gland Seal System (FSAR 14.2.12.2.75) - preoperational testing will be completed during power ascension.
Completion of the above items on the noted schedules does not degrade nuclear safety or require exceptions to the Technical Specifications.
In fact, completion of tests (b)-(g) requires for the most part hot, post-fuel load conditions.
In addition, contrary to the schedule currently indicated in the FSAR, the following preoperational tests will be completed prior to fuel load:
- -Airborne and Area Radiation Monitoring System (14.2.12.2.9)
Process and Effluent Radiation Monitoring System (14.2.12.2.10)
Circulating Water System (14.2.12.2.14)
Turbine Building Closed Cooling Water System-(14.2.12.2.15)
Turbine Building Ventilation System (14.2.12.2.25)
Fuel Handling and Storage System (14.2.12.2.52)
Fixed Incore Detector System (14.2.12.2.57)
Movable Incore Detector System (14.2.12.2.58)
Reactor Power Cutback System (14.2.12.2.62)
. Chemical Feed System (14.2.12.2.68)
Main Condenser Air Evacuation System (14.2.12.2.73)
(2)- FSAR Subsection 14.2.12.2.13 and the Response to NRC Question 640.11(2) should indicate that testing of the Nitrogen System will-use as acceptance-criteria that the system performs as described in:
-FSAR Subsection 9.3.9.
.=
'(3) The Response to NRC Question 640.13 should indicate that testing of the Turbine Bypass and Atmospheric Dump Valves is described in
-FSAR Subsection 14.2.12.3.29.
. (4) FSAR Subsection 14.2.12.3.16.4-(Chemistry) should be revised as per.
(5) FSAR Subsection 14.2.12.2.3 (Inverters) should be revised as per.
(6). The. test described in FSAR Subsection. 14.2.12.3.25 (Natural Circulation).will include the provisions noted on Attachment 4.
4 (7) FSAR Subsection 14.2.~12.3.28 (Verification of CPC Power-Distribution-Related Constants) erroneously indicates that items A,B, and C of the Test Method will be conducted at 50 percent power only; it should read that items A, B, and D will be conducted only at 50
. percent power.
J
'I t
A 1
1
[
~u I_-
ATTACHMENT 2 e(~
14.2.12.3.16.4 Acceptance Criteria 34 A.
Chemistry of the RCS and the steam generators is maintained within specifications in accordance with C"""" 28, 0:;ix:ti: E ;increin;,
M :1 2: St r Supply Sy:::: Ch::ictry M::::1, " vici:n 2.
FSAR Subsections 9.3.2 and 10.3.5.
18 B.
Appropriateness of established sampling frequencies is demonstrated in accordance with -05NPB-efh-Gembesti;;
- in
- : in;, ";:ler: St cr
^,-ryly Ojetce Ch ietry M;;.21, " vici 2.
Waterford 3 Chemistry Department procedures.
C.
Baseline data for RCS and steam generator chemistry are established.
D.
Procedures for sample collection and analysis are verified as ac-8 ceptable.
E.
Baseline activity levels for the RCS are established, Laboratory analyses agree satisfactorily - i:t :k4/-..; process radiation sveh t F.
monitory =3*ki- *'- ~ 'i- > cc r ::7 ef th: :::1 ::: : d th: ::di:
7 18 indicsk prope r NS PONJe,
b k
(
14.2-128 Amendment No. 34, (1/84)
ATTACitMENT 3 14.2.12.2.3 SAFETY-RELATED - INVERTERS gg 14.2.12.2.3.1 Objective l8 To verify proper operation of safety-related : '
- ::':L ::1:12-in-l 18 verters and transfer devices and to demonstrate that the inverters supply 15 full design capacity.
8 14.2.12.2.3.2 Prerequisites A.
Construction activities on the systems to be tested are complete.
18 B.
Plant systems required to support testing are operable, or temporary systems are installed and operable.
15 C.
Dummy load bank is available.
14.2.12.2.3.3 Special Prerequisites 8
A.
Diesel generator testing will be performed concurrently with this test.
Portions of the testing in 14.2.12.2.3.4 below will 1.e per-formed in conjunction with diesel generator testing (Subsections 29 14.2.12.2.17 and 14.2.12.2.93).
I 14.2.12.2.3.4 Test Method 8
A.
Verify all control logic.
15 B.
Verify the proper operation of the inverters, manual transfer l8 switches, frequency synchronization, and blocking diodes.
15 C.
Simulate normal and abnormal operating conditions and verify that the computer / annunciator reacts to these conditions.
l18 l 15 D.
Verify that each inverter automatically transfers the input to the
[8 battery upon loss of preferred power while maintaining uninterrupted l 18 power output.
E.
Using a dummy load bank, verify that the inverters supply 120V ac at 15 full load, using the normal power source.
F.
Place the battery chargers on equalise and verify that de equalizing voltage will not result in driving the inverter, relieving the 15-rectifier from carrying the inverter load.
l 29 Verify proper operation of all protective devices, controls, inter-C.
locks, alarms, and computer inputs.
l18
't I
4 l
14.2 Amendment No. 29, (10/82)
~
l
ATTACHMENT 4 4
NATURAL CIRCULATION 15 Objectives A.
To provide operator training in natural circulation under various plant conditions as described in the TMI Action Plan Item 1.G.I. and 31 clarified in NRC Letter of November 14, 1980.
B.
To evaluate natural circulation flow conditions and heat removal 15 capability.
Prerequisites l 10 The reactor is operating so as to provide a satisfactory heat source after 31 a trip. This test is performed in conjunction with the 80 percent loss of flow test (see Subsection 14.2.12.3.34).
Test Method A.
Secure all reactor coolant pumps and verify natural circulation flow.
B.
Demonstrate proper Reactor Coolant System (RCS) temperature flow and pressure control, pressurizer level control, and steam generator level control with natural circulation under the following conditions:
15 (1) Deenergized pressurizer heaters (2) Reduced RCS pressure (3) Isolated secondary side (feedwater and steam) of one steam generator Acceptance Criteria A.
Operator training requirements are met.
B.
Natural circulation cooling performs in accordance with design 18 predictions of CEN-128, Response of Combustion Engineering Nuclear Steam Supply System to Transients and Accidents.
NOTE: Additional natural circulation testing is described in Subsections 10 14.2.12.3.25, 14.2.12.3.35, and 14.2.12.3.41.
k 14.2-125a Amendment No 31, (3/83)
_ -._ _