ML20050B569
| ML20050B569 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 03/31/1982 |
| From: | Nichols T SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8204060068 | |
| Download: ML20050B569 (8) | |
Text
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i SOUTH CAROLINA ELECTRIC a GAS COMPANY g
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March 31, 1982 atmaar Mr. Harold R. Denton, Director q,
Office of Nuclear Reactor Regulation p
U. S. Nuclear Regulatory Camtission 4
Washington, D.C.
20555
Subject:
Virgil C. Sunmer Nuclear Station Docket No. 50/395 Iow Power Physicn Test Ref: (1)
Mr. Rahe's Ietter to Mr.
Denton dated July 9, 1981 (2)
Mr. Denton's letter to Mr. Rahe dated October 23, 1981 (3)
Mr. Nichols' letter to Mr. Denton dated October 31, 1980 and December 22, 1980 (4)
Mr. Tedesco's letters to Mr.
Nichols dated October 13, 1980 and November 14, 1980
Dear Mr. Denton:
The above reference documents between South Carolina Electric and Gas Conpany (SCE&G) and the Nuclear Regulatory Ccmnission (NRC) in regards to various special low power physics tests defined the requirements of the NRC staff and conmitments of SCE&G.
In addition to that information, Westinghouse Electric Corporation has evaluated the NRC staff requirenent in regards to special low power physics tests. Reference (1) above presented the Westinghouse position on the special low power physics tests which specifically address the concerns of natural circulation related issues. 'Ihe Westinghouse proposed program which was discussed in reference (1) was endorsed by the NRC in reference (2).
SCE&G is in agreement with the Westinghouse proposed method of addressing the NRC staff concerns in regards to the denonstration of natural circulation I
by neans of the tests detailed in reference (1).
As per our telephone agreement with Mr. Bill Long of the NRC on March 29, 1982, SCE&G intends to nodify the physics test program accordingly as specified in Attachments I and II.
Since the purpose of these tests is to generate qualification data for the plant simulator, each test will be conducted once. SCE&G will verify the Virgil C. Summer sinulator response using the results of these tests. A simulator will be used to meet the operator training objectives of Attachment II.
8204060068 820331 PDR ADOCK 05000395 A
e Mr. Harold Denton March 31, 1982 Page 2 SCE&G believes that the revised test program proposed by Attachment I will achieve the same training objectives required by the Commission (see Attachment II), but with significantly less inpact on critical path testing, plant operation, plant availability, and nost inportant, plant safety. None of the tests noted in Attachment I will require the defeat of any protection function, therefore ne special safety evaluations are required. Also, please find attached a revised FSAR Table 14.1-65a, " Augmented Iow-Power Tce t. " These changes will be reflected in the next FSAR amendment.
If there are any questions concerning this program, please contact us.
Very truly yours, Adh T. C. Nichols, Jr.
NBC/SFF/TCN/lkb Attachment j
cc:
V. C. Sunmar (w/o attach.)
G. H. Fischer (w/o attach.)
H. N. Cyrus T. C. Nichols, Jr.
(w/o attach.)
M. B. Whitaker, Jr.
J. P. O'Reilly H. T. Babb D. A. Nauman C. L. Ligon (N3RC) l W. A. Williams, Jr.
(
R. B. Clary l
O. S. Bradham A. R. Koon M. N. Browne G. J. Braddick J. C. Ruoff J. L. Skolds J. B. Knotts B. A. Bursey NPCF File l
TABLE 14.1-65a AUGMENTED LOW-POWER TEST 1.0 Objectives
.. \\
1.1 Demonstrate decay heat removal capability of natural circulation.
1.2 Determine the depressurization rate following a loss of pressurizer
,,j heaters for evaluation of the loss of all AC emergency procedure.
1.3 Demonstrate to the plant operators the effect of increased charging flow and reduced steam generator pressure on the saturation margin.
1.4 Demonstrate under simulated loss of offsite power conditions
~
that decay heat can be removed via the steam generators by-28 l
maintaining steam generator level with the Emergency Feedwater systeni.
^'
1.5 Demonstrate under simulated loss of onsite and offsite power conditions that decay heat can be rramoved via the steam generators by maintaining steam generator level with the Emergency Feedwater system.
l 1.6 Demonstrate boron mixing and reactor coolant system cooldown f
using natural circulation (credit for this objective may be 1:
taken for testing completed on a similar plant).
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L.7~ Train operatorsNn:
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natural circulation operations 1o~
3.
The use of auxiliary pressurizer spray C.
Loss of offsite, and loss of offsite and onsite AC power 14.1-120'a AMENDMENT 28 NOVEMBER, 1981 l
l
I TABLE 14.1-65a (Continu d) m 2.0 Prerequisites 2.1 The reactor coolant system and all emergency and auxiliary systems are at the conditions specified in the appropriate s
appreved test procedure.
2.2 Required signals for data collection and recording are 3
available.
2.3 Reactor Power is maintained less than or equal to five percent.
3.0 Test Method
( See otoched LSe 3.
The Natural Circulation Demonstration Test will consist of itiating the natural circulation mode at approItimately
(
rea or power and all reactor coolant pumps tripped.
ter suffic at period of stabilization, all pressurizer eaters will be t ed off to monitor RCS depressurizati rate.
28
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Once the sat ation margin has decreased to a edetermined amount RCS cha g flow will first'be inc ased and-steam flow increas to verity xheir aff t on RCS pressure and saturation margin. After sufficiept data has been col-lected under these condi ons, the SS will be returned to l
the original natural circul ion de., The effectiveness of the auxiliary pressurizer spra vill then be tested.
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% 3.2 Natural circulation with imulated lo of offsite AC power O
is-conducted at appro tely 1% reactor over. The steam dump selector switc will be in manual usin the steam pressure mode at contrcl.
ackup pressurizer heater gro a will be off.
All three rea or coolant pumps will be tripped.
CS pressure.
will be tained using manual control of the press izer control ater group and auxiliary spray. Steam line p saure will maintained using manual control of the steam dump g
- j sy es.
Steam generator level is maintained by manual contro the motor driven emergency feedwater pumps from the Control
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Room.
14.1-120 AMENDMENT 28 l
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i A'ITACIDElff I Virgil C. Sunner Nuclear Station Revised Special Iow Power Test Program 1.
In Hot Standby with the Reactor Coolant Punps supplying heat input to the secondary side, sinulate removal of onsite AC power sources and operate the plant utilizing manual control and the steam driven Emergency Feedwater Punp. HVAC to the punp roam is isolated to verify punp operability in this environment.
2.
After Fuel Loadirg, in Pot Standby, establish stable condition at -
Tno Ioad and 2235 psig with ICP B in operation.
Reduce pressure by turning off Pressurizer heaters noting depressurization rate.
Re-establish heaters and reduce pressure by use of auxiliary spray noting depressurization rate and effect on margin to saturation tenperature. At reduced pressure observe the effects of changes in charging flow and steam flow on margin to saturation tenperature.
3.
With the reactor critical at approximately 3% reactor power, place the plant in natural circulation unde observing the length of time for plant to stabilize, flow distribution, power distritmtion, and ability to maintain cooling mode.
4.
Perform Ioss-of-Offsite Power / Station Blackout Test with plant trip form 10-20% Rated Thernal Power. Operate plant establishina stable conditions in natural circulation using batteries and snergency diesels.
5.
Referencing boration and cooldown tests performed at Sequoyah I, North Anna II, Farley II, and Diablo Canyon I, verify similar plant response by parameter and plant conparison. Operator training for cooldown on natural circulation provided on a sinulator.
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O de M
s; t ATTACHMENT II I
I 13 e is t TEST PROGRAM OBJECTIVES 3g gg 3E d e:
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%o ma ma 1.
Observe Natural Circulation 3++
a) stabilization time 3
b) flow distribution 3
c) power distribution 3
d) maintain adequate cooling 3
2.
Observe depressurization rate without pressurizer heaters 2
3.
Observe depressurization rate with auxiliary spray 2
4.
Observe effect of changes in charging flow on Tsat 2
5.
Observe effect of changes in steam flow on Tsat 2
6.'
Maintain stable plant conditions utilizing battery and emergency diesel power supplies only 4
7.
Mr.intain stable plant conditions utilizing steam driven auxiliary feedwater pump and manually actuated equipment only 1
8.
Borate plant while in natural circulation 5*
l 9.
Cooldown plant while in natural circulation 5*
l
++ Test number of Attachment I where objective is covered.
l Control Room Operator training objective may be met by use of control room simulator with performance of verification test at plant or verification l
of simulator with previously performed Special Low Power Tests.
l l
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o INSERP-PAGE 14.1-120b 3.1 In Hot Standby with the Reactor Coolant Punps supplying heat input to the secondary side, simulate renoval of onsite AC power sources and operate the plant utilizing manual control and the steam driven Emergency Feedwater Punp. HVAC to the punp roan is isolated to verify punp operability in this environment.
3.2 After Fuel Ioading, but prior to Initial Criticality, establish stable condition at Tno Ioad and 2235 psig with ICP B in operation.
Reduce pressure by turning off Pressurizer heaters noting depressurization rate. Re-establish heaters and reduce pressure by use of auxiliary spray noting depressurization rate and effect on margin to saturation tenperature. At reduced pressure observe the effects of changes in charging flow and steam flow on margin to saturation tenperature.
3.3 With the reactor critical at approximately 3% reactor power, place the plant in natural circulation node observing the length of time for plant to stabilize, flow distribution, power /.stribution, and ability to maintain cooling node.
3.4 Perform Loss-of-Offsite Power / Station Blackout Test with plant trip form 10-20% Rated Thermal Power. Operate plant establishing stable conditions in natural circulation using batteries and energency diesels.
3.5 Referencing boration and cooldown tests performed at Sequoyah I, North Anna II, Farley II, and Diablo Canyon I, verify similar plant resmnse by parameter and plant conparison. Operator training for cooldown on natural circulation provided on a sinulator.
i
f TABLE 14.1-65a (Continuzd) 1 Nttural circulstion with simulatid logs of offeits and 3.3 te AC power is conducted with the reactor K,ff g.
on and al reactor coolant pumps operating to simulat decay heat. The team pump system is in manual usin the steam pressure mode control. Backup pressuri r heater groups will be off. RCS essure will be mai ained using manual control of the pressur er control ater group and auxiliary spray. The motor driven e rge y feedwater pumps will be in b
the off position and steam n' ator level being maintaine?:
T w
w via local control of th turbine ven emergency feedwater pump flow to the at generators.
3.4 Boron mixin uring cooldown on natural circul ion is determined by injec ng boron via the charging pumps into the eactor cool t system with no reactor coolant pumps running.
dequate 28 ron mixing will be verified by sampling and excore nucle instrumentation readings.
4.0 Acceptance Criteria 4.1 Natural circulation was established and maintained under steady state conditions.-i 211 rr ::.
SoFFicent la^t clofa. was collectal F6r plod S wJlerb-Vedicob, P
4.2 Op:::::: :_:ini ; d::in; ::::::1 circul: tic; ::: :::.,li:P.:d.
4.3 Adequate boron mixing during RCS cooldown on natural circulation has been proven at Virgil C. Summer Nuclear Station or credit
~
has been taken for this test performed on a similar plant.
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14.1-120)/
AMENDMENT 28 NOVEMBER, 1981
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