ML20041C527
| ML20041C527 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 02/23/1982 |
| From: | Nichols T SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8203020188 | |
| Download: ML20041C527 (14) | |
Text
,
SOUTH CAROLINA ELECTRIC & GAS COMPANY POST OFFICE SOE 764 COLUMaiA, SOUTH CAROLINA 29218 g
T. C. Niewots, Ja.
February 23, 1982 fV sf v.a p.o
,... o cuco,-c NucLtse 0.snase.s fY
~'.n Mr. Harold R. Danton, Director j
..,,l 1982s Office of Nuclear Reactor Regulation H
'~
U. S. Nuclear Regulatory Conmission Q U * ]' f' $ f ' tn *w r j7;'
Washingtcn, D. C.
20555
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Subject:
Virgil C. Surrmer Nuclear". xtaticn
- /
s, Docket No. 50/395
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FSAR Chapter 14 Changes
Dear Mr. Dmttn:
Ch February 12, 1982, a discussicn was held betwem Mr. H. B.
Claytcn of the NIC Staff and irud;ers of South Cardlina Electric and Gan Company (SCE&G) regarding several goposed changes to the FSAR Chapter 14. 'Ihe changes are shom cn the attached marked up pages.
Having received Mr. Claytcn's verbal concurrence, SCE&G formally docummts thcm in this letter. 'Ihey will be incorporated in the next FSAR ammdment.
If you have my questicns, please let us know.
Very truly yours, A
T. C. Nichols, Jr.
RBC:'ICN:lkb Attachmmt cc:
V. C. Sungner i
T. C. Nichols, Jr.
G. H. Fischer H. N. Cyrus H. T. Babb i
D. A. Nauman 3
M. B. M1itaker, Jr.
W. A. Williams, Jr.
O. S. Bradham R. B. Clary DCf M. N. Browne y
A. R. Kocn G. J. Braddick J. L. Skolds I
[
J. B. Knotts, Jr.
B. A. Bursey l
C. L. Ligcn (NSRC) l J. C. Ruoff J. P. O'Reilly l
NPCF File 82030201M 820223 PDR ADOCK 05000395 A
13.1.3.1.17 kastrumentSupervisor 12 1.
Five years of experience in instrumentation and control, of which one year.is in nuclear instrumentation and control at a l3 nuclear power plant. A minimum of two years of this five years
/
experience shall be related technical training. A maximum of fo"r years of this five years experience may be fulfilled by related technical or academic training.
13.1.3.1.18 Instrument Journeyman
~ITVO 1.
Eiseeeayears of instrument maintenance experience or applicable industrial experience.
30
- 2. One y'eGr-oF t-clafed Yedo*.cc.l YrciM 4].
13.1.3.1.19 Maintenance Engineer 12 1.
One year of power plant experience.
(
2.
A baccalaureate degree in mechanical or electrical engineering is desirable.
13.1.3.1.20 chemistry Supervisor s
[
12 1.
Five years of chemistry experience of which a minimum of one year shall be in radiochemistry at a nuclear power plant. A 3
minimum of two years of this five years experience shall De related technical training. A maximum of four years of this five years experience may be fulfilled by related technical or academic training.
2.
High school education or equivalent. A degree in chemistry or chemical engineering is desirable.
AMENDMENT F30
"-1-29
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, '_" 7 3 -
M a rch lif t
. - -. ~.... -..
LIST OF TABLES (Continued)
Title Page Table _
p 14.1-76 3elow-Bank Rod Test 14.1-135 Qip fron1 l x % F 0'
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N Plant,L;;; ;f 1;;;.ric.1 Lv.J 14.1-137 i
14.1-77 14.1-78 Loss of Offsite Power 14.1-139 14.1-79 Shutdown from Outside the Control Room 14.1-140 14.1-79a Emergency Lighting 14.1-140aa 17 14.1-79b Heat Tracing for Safety-Related 14.1-140b Outdoor Piping s
6 14.1-79c Pressure Boundary Integrity Test 14.1-140c 14.1-79d Seismic Instrumentation 14.1-140d 14.1-80 Power Ascension Test Program 14.1-141 14.1-81 Initial Test Program Schedule 14.1-142 3
14.1-82 Generic Flush Procedure 14.1-143 14.1-83 Generic Hydrostatic / Pneumatic Test 14.1-144 10 14.1-84 Instrument Control Procedure 14.1-146 14.1-85 Functional Test 14.1-147 14.1-86 Steam Genrator Power Operated Relief Valve 14.1-148
(
14-h AMENDMENT x
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results of these tests show that the plant follows its predicted nuclear I
parameters and can be operated at rated capacity without endangering gi the health or safety of the public.
Some of' the tests described in Regulatory Guide 1.68 are considered
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[tij preoperational tests, but because of their requirements, are performed
-u during startup testing. An example is scram perforinance of control rods.
Ihis can only be done after the core is loaded and the vessel T.i head is on; although this test appears in the preoperational section of W
R,M the guide.
b Uj To assure quality control, procedures used in testing are written and v.
approved in accordance with Section 14.1.1.
Changes made to approved fj, procedures are in accordance with Section 14.1.2.
The use of plant f.
3 Procedures is discussed in Section 14.1.5.
Compliance with regulatory a
guides is discussed in Appendix 3A.
1.'
The Manager Virgil C. Sener Nuclear Station is responsible for the development, administration and conduct of the test program.
The test program is conducted by a startup group which is organized specifically for performing the initial tests and startup of the plant.
After com-mercial operation this group will be disbanded.
The startup group is described in more detail in Section 14.1.1.4.
i The initial test program schetlule is presented as Table 14.1-81.
1 14.1.1 ADMINISTRATIVE PROCEDURES (TESTING) 14.1.1.1 Development of Procedures 8
The preparation of Phase I, II an III test procedures is the responsibi-QadT /w 30l lity of the, LJ...1;agr or-h>s1 m p n S p ;ynee.;;;:n(qualification described in 15 Section 13.1.3).
The Startup Supervisor may assume these duties for 30 14.1-2 AMENDME!C W
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-seneMua, m s
Mcrc h,1982-
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'. 4 13 or their designated alternates, each having at least the qualifications 2A M
of a Lead Systems Supervisor as described in Section 14.1.1.4, for
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{j review.
The Startup Supervisor may also send the procedure to designated
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groups or persons for review.
These designated groups ur persons may
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include Nuclear Engineering personnel, Quality Assurance personnel, f.}
the OpYr$tionsSu;;r-::;r, Maintenan f r-1:n and/or Technical
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Support Su; r ? c. Minimum qualifications for Nuclear Engineering and
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plant personnel assigned to review Phase II Test Procedures are provided Mh in Section 13.1.
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The reviewers examine the procedure for correctness and
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comment as necessary. The procedure with comments is then returned to N
the originator for resolution / incorporation of comments.
i.
8 When comments are resolved / incorporated, the procedure is forwarded to the Startup 2
h b
Supervisor.
The Startup Supervisor or his designee signs Q
the procedure recommending approval.
The procedure is transmitted to 17 the P'lant Manager or his designee for his approval.
s The reparation of Phase III Test
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asTa.CMonogr-Procedures will be the responsibility p
of t ATechnicar Support Sup;r-Escr. or his designated alternate, who
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will asshTer;SafysrT personnel,the responsibility for the prehrg)at i
h ar
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orgna procedures td/.e:t Superci;;rs.
y TheA.~ct Sup'-'E::; o) prepares the 15 assigned procedure in the prescribed format and submits the procedure for distribution.
The procedure (s) will be reviewed and approved as per Plant Administrative Procedures (FSAR Chapter 13 and Technical Specifi-cations Section 6).
i I
Test procedures are available to NRC inspection personnels 30 days prio
-s to the scheduled performance of the activity
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, by not less than 90 days prior to the scheduled core loading date.
NRC possession of procedures shall not impede revision, review or refinement of the procedures.
m The format for Phase II and III test procedures is as follows:
~
l m
l 14.1-3a AMENDMENT 17 FEBRUARY, 1980
3 f
14.1.1.2 Execution of Test Procedures Prior to the start of the initial testing program, the Virgil C. Summer
. Nuclear Station Operations Department arranges itself into a startup group which is more suited for the initial testing program. This organization is headed by the, Manager Virgil C. Summer Nuclear Station.
15 A Startup Supervisor who reports to the Manager Virgil C. Summer Nuclear Station organizes and directs the startup program. The Startup Supervi-sor appoints a test supervisor for each test. More than one test super-
]
visor may be appointed. The test supervisor ensures that the test is conducted according to the test procedure. Qualified test personnel are
~
assigned by the Startup Supervisor to perform the tests. The personnel perform the test work under the supervision of the test supervisor.
Prior to fuel loading all Phase I (component and construction) tests and Phase II (Pre-Operational and Accept Ance) tests are scheduled to be conducted and the results reviewed and approved in accordance with I
approved administrative procedures, i
A limited number of test deficiencies may exist at the scheduled core 8
loading date. These test deficiencies will be evaluated and categorized.
j Appropriate hold points in the Phase III (Initial Startup) Test Program will be identified. The applicable deficiencies will be resolved prior to proceeding with the Phase III Test-Program.
L During the power ascension phase of testing, certain data a gal e
I y
by the test supervisor and the results are reviewed by the -1:rt sf..,
15
, or Ms desenet Co--...;;
before power is increased to the next higher plateau.
Analysis of data includes checking radial flux for symmetry, verifying that axial flux is within predicted values,. checking effluent radioacti-2 vity, monitoring system operation, and checking power level and nuclear instrumentation by using a heat balance. Before power is increased to a higher plateau, the high flux trip is reset to a value no greater than 6
20 percent beyond the next power level. Approval'of the Plant Manager or his designated alternate must be obtained before increasing power to L
M " ' M "" A f'*" 'S Yg fee-tenfs., plateau. Ary**l *F h 4-P *hd P pom)U inWCW l
30 the next 04tson o # -tA 4 Sftirtug pmqm*$ or I
14.1-6 AMENDMENT F1-3D SEDP"M ;, 1079
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14.1.1.3 Revisv, Evhluntion, cnd Approv11 of Tant Resu'.tr Af ter a Phase I test is completed and the data is compiled, the Test,
Supervisor will review the test results and compare them to the appli-cable Acceptance Criteria.
If he is satisfied that the test results are satis f actory, he will submit the test to the Lead Systems Supervisor.
8 The Lead Systems Supervisor will be responsible for reviewing the test results and comparing them to the applicable Acceptance Criteria.
If he is satisfied that the test results are acceptable, he vill approve the test data.
If the test results are not satisfactory, the Lead Systems Supervisor will recommend to the Startup Supervisor what actions are necessary.
After a Phase II test is completed and the data is compiled, the Startup Supervisor will ' assign the Westinghouse Startup Representative, the 15 Gilbert Associates Startup Representative or their designated alter-nates,'each having qualifications of a Lead Systems Supervisor as described in Section 14.1.1.4, to rev,iew the tes t results. The assigned 13 personnel will revies the test results and compare them to the appli-cable acceptance criteria specified in the procedure, and forward the test results to the Startup Superviser. The Startup Supervisor or designated alternate will then review the test results and, if accept-able, sign the test results recommending approval to the Menager Virgil C. Summer Nuclear Station.
The test results are then sent to the Man-13 ager Virgil C. Summer Nuclear Station for his review and approval.
If test results are not acceptable, the personnel assigned to review the
(
data recommends to the Startup Supervisor what actions are necessary.
i These actions are outlined in more detail in Section 14.1.2.1.
After a Phase III Test is completed and the data is compiled, the Lead l
Phase III Test Supervisor will place the review of the completed test procedure on the adgenda of the Plant Safety Review Committee Meeting for consideration for approval of the test resultsg rc:::t4 3. ^- for 3C) l
- ary articn
- i: tchca.
If the review of the test results during the Plant Safety Review Committee Meeting show that the test results are IS s-I acceptable, the Plant Safety Review Co=mittee Chairman signs a procedure recommending approval, the procedure is transmitted to the Plant Manager
'l 28 or his designated alternate for his approval.
l 36 l
AMENDMENT X 14.1-7
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,mm.
.~ u.2aan, 1204,-
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l gf and testing of their equipment. Technical services are available from
'7
(.
Westinghouse, Gilbert and Daniel.
The Manager Virgil C. Sucuner Nuclear Station, in addition to his other l15 duties outlined in Section 13.1.2.2, has overall responsibility for Phase 3
Q' II and Phase III of the initial test program. He is responsible fo'r the
~
development /^ t e i ? of the test procedures, the administration and l3o conduct of the test and the review and actions taken on the test results. The qualifications of the Plant Manager are outlined in Sec-e tion 13.1.3.
The Startup Supervisor is under the supervision of the Manager Virgil C.
15 Sununer Nuclear Station and ensures effective administrative control and implementation of the test program. The Startup Supervisor meets one of the following qualifications.
1.
A graduate of a four-year engineering or science college or univer-J sity plus five years of experience in operation, testing or inspec-tion of power plant, nuclear plant, heavy industrial or other similar equipment or facilites. At least two years of this expe-rience should be associated with nuclear facilities; or if not, the individual shall have training sufficient to acquaint him thoroughly with the safety aspects of a nuclear facility.
2.
A h'igh school graduate or equivalent, plus ten years of experience in operation, testing or inspection of power plant, nuclear plant, heavy industrial or other similar equipment or facilities. At least two years of this experience should be associated with nuclear facilities; or if not, the individual shall have training sufficient to acquaint him thoroughly with the safety aspects of a nuclear facility.
So 14.1-8 AMENDMENT #f
-E E T C '".aE R, 1379 Aiarch /982.
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WO The measurements are made at low power and primarily at or near operat-15lE9
.; g.p ing temperature and pressure.
Measure =ents, to include verification of
-s calculated values of control rod assembly group reactivity worths, of rm l
moderator temperature coefficient under various core conditions, of differential boron concentration reactivity worth and of critical boron concentrations as functions of control rod assembly group configuration i
are made.
In addition, measurements of the relative power distributions d
are mada.
Concurrent tests are conducted on the inst'rumentation includ-ing the source and intermediate range nuclear channels.
M C.
kUYS M F; In accordance with NUREG 0737, item I.G.1, a discussion of the special 1;pny L w Power Testing to be performed at the Virgil C'. Summer station has 23 9,x?5 been submitted to the NRC under separate cover letters dated 10/31/80, yw L
[.$.9s 12/2/80 and 12/22/80.
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-f Detailed procedures are prepared to specify the sequence of tests and
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measurements to be conducted and the conditions under which each is to p.j be performed to ensure both safety of operation and the relevancy and consistency of the results obtained.
If significant deviations from b@3 design predictions exist, unacceptable behavior is revealed, or apparent w-n.
anomalies develop, i ; ;;in, ': cu;palcl.
. 2 =1,:i* a review by e
qualified personne performed.
The Plant Manager may detcrmine that 30 Plan a review by the "uchrASafety Review Committee--Ca per-Occi.ivu 13.'. 2.2)-
- * *5 E'O PMN '
l-isappropriatepriortN-Ndhi f t:
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14.1.4.5 Power Ascension l
When the operating characteristics of the reactor and plant are verified j
by the low power testing, a program of power level escalacion in suc-cessive stages brings the plant to its full rated power level.
Prior to starting to the next higher power plateau, as defined by the start-l up test program, management approval shall be obtained, also, the high flux trip shall be reset to a value no greater than 20 percent beyond the next power level.
During the power escalation, a predetermined test program is followed to verify that the reactor and plant are performing as expected.
The minimum test requirements for each successive stage of power escalation are specified.
N s
AMENDMENT #1
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14.1-24 y }'/p,jjal
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-s TABLE 14,1-75 R,0D DROP TEST C,,
1.0 objective Io demonstrate the operations of the negative rate trip circuitry f
f
+ws
- o indetectingtfm0lhnesusefinsertion of enerod cluster control assemblies. -
15 g 2.0 Prerequisites 2.1 All power range nuclear instrumentation channels are operable.
2.2 The reactor is at the steady-state power level specified in the procedure with the controll'ing bank near the full power insertion limit.
2.3 Pertinent parameters to be measured are connected to recording devices.
3.0 Test Methods 7"s*v o to b 3.1 ^ : :;d'from a common group most difficult to detect by excore g
are SamoHamusif detectorsduetolowworthandcorelocation,iagroppedby removing voltage to both the moveable and stationary gripper 13 i
coils of the designated rod.
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3.2 Following the transient, recorded data is evaluated for system and instrumentation response, so l
14.1-133 AMENDMENT M 1
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March,196L
A$.NDMENT3 #
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MARCE, 1978-
/yy;2 TABLE 14.1-77 7~ RIP FRon 100 lc VOWE2_
PLANNLCC C Cr L"CT"ICf.'
'_Of_. S f-x 1.0 objective I WSE W $
W T= _ _ _- C._
g-~,eerne eke -bilit, c
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ishmut.. mom;c.-/: rb d d *v4
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1.2 T: :;nlue:: the i... f.;icn 'ct.;cen cca;;ci ofoLe~ oum so cn;c to th;
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2.0 Prerequisites 2.1 The various' control systems are in the automatic mode and functioning properly.
s-4
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2.2 The reactor is steady state at 100 percent power, with the rods in the maneuvering band.
2.3 Pressurizer and main steam safety and relief valves are in service and operable.
2.4 Pertinent parameters to be ceasured are connected to recording devices.-
3.0 Test Methods
' " ' Y* I'9 7,,;y;s fe a p/ont N.'/ Jy m"o//f
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3.2 Pertinent parameters are recorded on recording devices.
14.1-137
INSERT A - Page 14.1-137 I
1.1 To demonstrate the ability of the primary and secondary plant and the plant automatic control systems to sustain a trip from 100% power and to bring the plant to a stable
}3()
condition following the transient.
Ic2 To determine the overall response time of the reactor coolant hot leg resistance temperature detectors.
1.3 To obtain data which is to be evaluated to determine if changes in the control system setpoints are warranted to improve transient response based on actual plant operation.
r 9
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TABLE 14.1-77 (Continued)
TRIP FRom 100% POWEE-PML^CC 07 MRFA{ {ggy _
30 j
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3.3 Following the transient, recorded data is evaluated for system
)
and controller response and possible abnormalities.
4.0 Acceptance Criteria 4.1 The parameters recorded are not more limiting than those in the setpoint study document.
13 4
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36 14.1-138 AMENDMENT W W R E, 1979-M a rc k R 8 2.
TABLE 14.1-78 p
LOSS OF OFFSITE POWER 1.0 Objective fv To demonstrate that the necessary equipment, controls, and indi-cation are available following the isolation of the offsite power E
distribution system to remove decay heat from the core using only
(.M-*i emergencyhowersupplies.
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2 kA D
.0 Prerequisites w
N The plant is at a steady-state condition with greater than 10 4.Q}
percent (10%) generator output.
g Q 3.0 Test Methods Up 13 nyg?
. (-. 0N gf F 1-3.1
^: ;12t: los ef offsite p e.- by renuelly ep:.i h
-:::::r cM.-ciuuu. usa..cr, th- -- rg-ncym ua,iliary oii-o p
t circuit Luc ict, 61 c min generator breaxer ou Fthe hue IDA-N4 N
and IN
'_2 YJ/ fu=J fivm che engineet cJ..fcty f=
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e 0 4o
< rr e mm.cn.
N O 07
\\V 3.2 Using approved operating procedures, bring the plant to a hot standby condition and maintain the plant in a hot stand-1 by condition for at least thirty (30) minutes using only emergency on-site power sources.
(,
l 4.0 Acceptance Criteria The hot standby condition is achieved and maintained for at least
. thirty (30) minutes using only emergency on-site power sources.
t 3D 14.1-139 AMENDMENT -E3'
-A""IL, 1070 -
Morrd, 8 B2.
-