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=Text=
=Text=
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south CAROLINA Electric & GAS COMPANY eost ore.ca som     1,.-
south CAROLINA Electric & GAS COMPANY eost ore.ca som 1,.-
CotuunA. south CAROUN A 29218 O. W. DixoN. Jm.
CotuunA. south CAROUN A 29218 O. W. DixoN. Jm.
vice P e siotNT nueu.. o......o~.
vice P e siotNT nueu.. o......o~.
July 7, 1982 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington D.C. 20555
July 7, 1982 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S.
Nuclear Regulatory Commission Washington D.C.
20555


==Subject:==
==Subject:==
Virgil C. Summer Nuclear Station Docket No. 50/395 Chapter 14 FSAR Tests
Virgil C.
Summer Nuclear Station Docket No. 50/395 Chapter 14 FSAR Tests


==Dear Mr. Denton:==
==Dear Mr. Denton:==
Several changes to FSAR Chapter 14 were discussed with Mr.
Several changes to FSAR Chapter 14 were discussed with Mr.
William Long of your staff on July 7, 1982. These changes involve FSAR Tables 14.1-58, " Reactor Coolant System Flow Measurement",
William Long of your staff on July 7, 1982. These changes involve FSAR Tables 14.1-58, " Reactor Coolant System Flow Measurement",
and 14.1-75, " Rod Drop Test". Please find attached these " marked up" pages which contain the changes as agreed to by Mr. Long.
and 14.1-75, " Rod Drop Test".
Please find attached these " marked up" pages which contain the changes as agreed to by Mr. Long.
If you have any questions please let us know.
If you have any questions please let us know.
Very truly yours, 77 -
Very truly yours, 77
                                                                            .,p O. W. lxo , Jr.
.,p O.
RBC:OWD/fjc cc:     V. C. Summer                 R. B. Clary G. H.       F!scher                 O. S. Bradham H. N.       Cyrus                   A. R. Koon T. C.       Nichols, Jr.           M. N. Browne O. W.       Dixon, Jr.             G. J. Braddick M. B. Whitaker, Jr.                 J. L. Skolds J. P. O'Reilly                     J. B. Knotts, Jr.
W.
H. T. Babb                         F. Mangan
lxo, Jr.
;              D. A. Nau man                     B. A. Bursey l             C. L. Ligon (NSRC)                 NPCF W. A. Williams, Jr.                 File 8207150540 820707 PDR ADOCK 05000395 A                       PDR
RBC:OWD/fjc cc:
V.
C.
Summer R.
B.
Clary G.
H. F!scher O.
S. Bradham H.
N.
Cyrus A.
R.
Koon T.
C.
Nichols, Jr.
M.
N.
Browne O.
W.
Dixon, Jr.
G.
J.
Braddick M.
B.
Whitaker, Jr.
J.
L.
Skolds J.
P.
O'Reilly J.
B.
Knotts, Jr.
H.
T.
Babb F.
Mangan D.
A.
Nau man B.
A.
Bursey l
C.
L. Ligon (NSRC)
NPCF W.
A.
Williams, Jr.
File 8207150540 820707 PDR ADOCK 05000395 A
PDR


            ~
~
TABLE 14.1-58 REACTOR COOLANT SYSTEM FLOW MEASURE >ENT 1.0 Objective i
TABLE 14.1-58 REACTOR COOLANT SYSTEM FLOW MEASURE >ENT 1.0 Objective i
Obtain the data to compute actual reactor coolant system flow rates as they relate to the design flow rates.
Obtain the data to compute actual reactor coolant system flow rates as they relate to the design flow rates.
2.0   Prefequisites 2.1 Core installed.                .
2.0 Prefequisites 2.1 Core installed.
2.2 Reactor plant is in hot standby condition with all control rods l   15 fully inserted.
2.2 Reactor plant is in hot standby condition with all control rods l
15 fully inserted.
2.3 Reactor coolant pumps operable.
2.3 Reactor coolant pumps operable.
3.0   Test Methods 6
3.0 Test Methods 6
3.1 Measure loop temperatures, loop elbow tap 6p's and reactor coolant pump input power and speed for various configurations of reactor coolant pumps.
3.1 Measure loop temperatures, loop elbow tap 6p's and reactor coolant pump input power and speed for various configurations of reactor coolant pumps.
3.2 Compute actual reactor coolant system flow race. Density vari-ation of cold leg fluid will be accounted for in the data             15 reduction method to provide direct comparison to full power conditions.
3.2 Compute actual reactor coolant system flow race. Density vari-ation of cold leg fluid will be accounted for in the data 15 reduction method to provide direct comparison to full power conditions.
      ,      4.0   Acceptance Criteria i
4.0 Acceptance Criteria i
I (l Reactor coolant system flow rates are determined to be greater than i
(l Reactor coolant system flow rates are determined to be greater than I
or egual to the thermal design minimum and less than or equal to s             the mechanical design maximum as per FSAR Table 5.1-1.                     15 b.2 U YL CHkcHes QS $eScHbeN IH ku[ '*S no Y Ae power Level all k. reskc}ed % % reded)                               33 l                   1herme { poacr && k mewed @ ache Coolo%'
i or egual to the thermal design minimum and less than or equal to s
        .            Gysk flow m$e. a);Il O'EEE W                                           ,
the mechanical design maximum as per FSAR Table 5.1-1.
AMENDMENT 8 33 mr==,       n:^-
15 Y
l 30 ly,1982.
CHkcHe QS $eScHbeN IH ku[
L
'*S b.2 U YL no Ae power Level all k. reskc}ed % % reded) s 33 l
1herme { poacr && k mewed @ ache Coolo%'
Gysk flow m$e. a);Il O'EEE W AMENDMENT 8 33 mr==,
n : ^ -
30 ly,1982.
l L


                                    - .            ..                            c 23 TABLE 14.1-75               AMENDMENT.30"
c 23 TABLE 14.1-75 AMENDMENT.30"
                                                                                  "!.2011r 1982
"!.2011r 1982 ROD DROP TEST
    ;                                                ROD DROP TEST                     [
[
1.0 Obj ect ive 4
1.0 Obj ect ive 4
To demonstrate the operations of the negative rate trip circuitry
To demonstrate the operations of the negative rate trip circuitry in detecting the simultaneous insertion of two cluster control assemblies.
            ,          in detecting the simultaneous insertion of two cluster control assemblies.                                                                                     30 2.0 Pre requis ite s 2.1 All power range nuclear instrumentation channels are operable.
30 2.0 Pre requis ite s 2.1 All power range nuclear instrumentation channels are operable.
2.2 The reac tor is at the steady-state power level specified in the procedure with the controlling bank near the full power inser-tion limit.
2.2 The reac tor is at the steady-state power level specified in the procedure with the controlling bank near the full power inser-tion limit.
2.3 Pertinent parameters to be measured are connected to recording device s .
2.3 Pertinent parameters to be measured are connected to recording device s.
3.0 Te s t Me thods S.E ,% r Two rods from a common group most difficult to detect by excore                           i de tectors due to low worth and core location, are simulta-                               30 l
3.0 Te s t Me thods S.E,% r Two rods from a common group most difficult to detect by excore i
neously dropped by removing voltage to both the moveable and stationary gripper coils of the designated rod.                                           15 l
de tectors due to low worth and core location, are simulta-l 30 neously dropped by removing voltage to both the moveable and 15 l
3.3 M Fo11owing the transient, recorded data is evaluated for system                               33
stationary gripper coils of the designated rod.
                                                                                                                )
3.3 M Fo11owing the transient, recorded data is evaluated for system 33
)
and instrumentation response.
and instrumentation response.
p                             r b
p r
14.1-133
b 14.1-133
(                       3.1 A u E se power re.y nuekr msfev medahon c!w.,n tl y                               fosdhu: a n el n e3divr rede 4v.m are defM+al w,%
(
3.1 A u E se power re.y nuekr msfev medahon c!w.,n tl y
fosdhu: a n el n e3divr rede 4v.m are defM+al w,%
todromeh% sefvp b mode % neybve rede + ;p hs k W s.
todromeh% sefvp b mode % neybve rede + ;p hs k W s.


Line 75: Line 132:
ROD DROP TEST C
ROD DROP TEST C
4.0 Acceptance Criteria
4.0 Acceptance Criteria
            .1 Thc reacter trip     a result of th   22;; ti   rate trip.
.1 Thc reacter trip a result of th 22;; ti rate trip.
            ' .2 Stcan gcncrator-and--prc ur-incr sfet-j ;;1:c: dc :t lift.             33
'.2 Stcan gcncrator-and--prc ur-incr sfet-j ;;1:c: dc :t lift.
33
_.; carety tujectica is act initi;t:d.
_.; carety tujectica is act initi;t:d.
4.1 The neybve rafe k'P Ci'** ; bY 'S '' n;5'"I'N n
4.1 The neybve rafe k'P Ci'** ; bY
ct mi ni mum oF fra. power yany nuclear indromen brhen chca n els as a           reso l+   e> F 5>rwHaneously     d wpp m3 + s skt               gods.
'S ' n;5'"I'N n
ct mi ni mum oF fra. power yany nuclear indromen brhen chca n els as a reso l+
e> F 5>rwHaneously d wpp m3 + s skt gods.
L f
L f
h 14.1-134                         ON*   **d7 33
h 14.1-134 ON*
                                                                          -J>ly ,/9f2
**d7 33
                                                                                    -}}
-J>l,/9f2 y
-}}

Latest revision as of 16:22, 17 December 2024

Forwards Changes to Chapter 14,FSAR Tables 14.1-58, RCS Flow Measurement, & 14.1-75, Rod Drop Test, Per 820707 Discussion
ML20055A168
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 07/07/1982
From: Dixon O
SOUTH CAROLINA ELECTRIC & GAS CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
NUDOCS 8207150540
Download: ML20055A168 (9)
v • d • e


Text

south CAROLINA Electric & GAS COMPANY eost ore.ca som 1,.-

CotuunA. south CAROUN A 29218 O. W. DixoN. Jm.

vice P e siotNT nueu.. o......o~.

July 7, 1982 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S.

Nuclear Regulatory Commission Washington D.C.

20555

Subject:

Virgil C.

Summer Nuclear Station Docket No. 50/395 Chapter 14 FSAR Tests

Dear Mr. Denton:

Several changes to FSAR Chapter 14 were discussed with Mr.

William Long of your staff on July 7, 1982. These changes involve FSAR Tables 14.1-58, " Reactor Coolant System Flow Measurement",

and 14.1-75, " Rod Drop Test".

Please find attached these " marked up" pages which contain the changes as agreed to by Mr. Long.

If you have any questions please let us know.

Very truly yours, 77

.,p O.

W.

lxo, Jr.

RBC:OWD/fjc cc:

V.

C.

Summer R.

B.

Clary G.

H. F!scher O.

S. Bradham H.

N.

Cyrus A.

R.

Koon T.

C.

Nichols, Jr.

M.

N.

Browne O.

W.

Dixon, Jr.

G.

J.

Braddick M.

B.

Whitaker, Jr.

J.

L.

Skolds J.

P.

O'Reilly J.

B.

Knotts, Jr.

H.

T.

Babb F.

Mangan D.

A.

Nau man B.

A.

Bursey l

C.

L. Ligon (NSRC)

NPCF W.

A.

Williams, Jr.

File 8207150540 820707 PDR ADOCK 05000395 A

PDR

~

TABLE 14.1-58 REACTOR COOLANT SYSTEM FLOW MEASURE >ENT 1.0 Objective i

Obtain the data to compute actual reactor coolant system flow rates as they relate to the design flow rates.

2.0 Prefequisites 2.1 Core installed.

2.2 Reactor plant is in hot standby condition with all control rods l

15 fully inserted.

2.3 Reactor coolant pumps operable.

3.0 Test Methods 6

3.1 Measure loop temperatures, loop elbow tap 6p's and reactor coolant pump input power and speed for various configurations of reactor coolant pumps.

3.2 Compute actual reactor coolant system flow race. Density vari-ation of cold leg fluid will be accounted for in the data 15 reduction method to provide direct comparison to full power conditions.

4.0 Acceptance Criteria i

(l Reactor coolant system flow rates are determined to be greater than I

i or egual to the thermal design minimum and less than or equal to s

the mechanical design maximum as per FSAR Table 5.1-1.

15 Y

CHkcHe QS $eScHbeN IH ku[

'*S b.2 U YL no Ae power Level all k. reskc}ed % % reded) s 33 l

1herme { poacr && k mewed @ ache Coolo%'

Gysk flow m$e. a);Il O'EEE W AMENDMENT 8 33 mr==,

n : ^ -

30 ly,1982.

l L

c 23 TABLE 14.1-75 AMENDMENT.30"

"!.2011r 1982 ROD DROP TEST

[

1.0 Obj ect ive 4

To demonstrate the operations of the negative rate trip circuitry in detecting the simultaneous insertion of two cluster control assemblies.

30 2.0 Pre requis ite s 2.1 All power range nuclear instrumentation channels are operable.

2.2 The reac tor is at the steady-state power level specified in the procedure with the controlling bank near the full power inser-tion limit.

2.3 Pertinent parameters to be measured are connected to recording device s.

3.0 Te s t Me thods S.E,% r Two rods from a common group most difficult to detect by excore i

de tectors due to low worth and core location, are simulta-l 30 neously dropped by removing voltage to both the moveable and 15 l

stationary gripper coils of the designated rod.

3.3 M Fo11owing the transient, recorded data is evaluated for system 33

)

and instrumentation response.

p r

b 14.1-133

(

3.1 A u E se power re.y nuekr msfev medahon c!w.,n tl y

fosdhu: a n el n e3divr rede 4v.m are defM+al w,%

todromeh% sefvp b mode % neybve rede + ;p hs k W s.

TABLE 14.1-75 (Continued)

ROD DROP TEST C

4.0 Acceptance Criteria

.1 Thc reacter trip a result of th 22;; ti rate trip.

'.2 Stcan gcncrator-and--prc ur-incr sfet-j ;;1:c: dc :t lift.

33

_.; carety tujectica is act initi;t:d.

4.1 The neybve rafe k'P Ci'** ; bY

'S ' n;5'"I'N n

ct mi ni mum oF fra. power yany nuclear indromen brhen chca n els as a reso l+

e> F 5>rwHaneously d wpp m3 + s skt gods.

L f

h 14.1-134 ON*

    • d7 33

-J>l,/9f2 y

-

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