ML20147H378

Ack Reciept of Faxes from Licensee Re Restart Criteria for Rod Drop Test Planned for Apr 1997 & Info Related to Bulletin 96-01

ML20147H378
Person / Time
Site:	South Texas
Issue date:	03/31/1997
From:	Alexion T NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
IEB-96-001, IEB-96-1, NUDOCS 9704030097
Download: ML20147H378 (22)

Text

_ _. _ _.

e 4

March 31, 1997

\\

MEMORANDUM T0:

PD IV-1 File FROM:

Tom Alexion

SUBJECT:

LICENSEE'S RESTART CRITERIA FOR R0D DROP TEST PLANNED FOR APRIL 1997 AND OTHER INFORMATION RELATED TO BULLETIN 96-01, SOUTH TEXAS PROJECT, UNIT 1 (TAC NO. M95043) j I received the attached faxes from the licensee.

Docket No. 50-498 j

Attachment:

Faxes from Licensee DISTRIBUTION:

Docket File PUBLIC (PDR)

WBeckner TAlexion Document Name: STP95043.NOT 0FC PM/PD4-1 #M,

NAME TAlexion/vw N/ /97 3I DATE..

COPY (YES)NO OFFIttAL RECORD COPY

/

)

\\

()Fw ^

i i

NHC FRf CENTHICOPY 9704030097 970331 PDR ADOCK 05000498 G

PDR

j Unit 1 Cycle 7 Inceanplete RCCA Insertion Evaluation Criteris for April 1997 Rod Drop Testing r

f

\\

f Deka Rod Drop 11am (n~' Drop 11me Increase Since Last Test) 2 4

Tech SpecIJmit ReviewIAnit Immediam RaourtIJant not apphcable s0.3 see s0.1see i

f Eod Drop 11sne Machaient SWeion 3.1.3A)

) g TeMpecIknit Review 1& nit Immadise RamartLimit l

e s 2.4 see s2.0sec g 1.83 see i

i i

Shutdown Marsin Technical SMcation 3.1.1.1)- AWkle for no4and Tava* '

SafetyEvaluation(SE) Limit RswewIknit Immadine RestartIhk CA,sy1 56 RCCAss 11 steps 12RCCAss6 seeps 6 RCCAss 6 steps,and NoIRIinV5H feels 25 gwWmeu andSanderefuelsso dhmu s

Category 2 20RCCA:s 16 steps 3 ROCAss12 seeps 6ROCAss 6 seeps,and I

plus NoIRIin V5H fbeis 25 gwdhntu 6ROCAss6 seeps and standard fuels 30gwdhntu Casesory 3 12 ROCAs s22 seeps 1 ROCAs 18 steps 6 ROCAss6 seps,and i

plus NoIRIin V5H Anels 25 gwdhntu 6ROCAss 6 steps and Standard fuels 30 god /mtu

• All Simidown Margm limits assume da highest reactivity merth rod is ibDy withdrawn. Esfor to USQE 9tLOO25 for further casegory details. Rod posidons 1br the Review and immadiam Restart limits are based on DRP! indication and account for DRPI syssem uncertamty (* 4 sosps).

ATTACHMENT l

Page I of 2 tgedB *d 06EO E46 EIS

'JH1SH3317 WO3 DnN LS:90 4661 W

te a wiol s,-

~

Unit 1 Cycle 7 Incomplete RCCA Inserti:n Evaluati:n Crite i

n for i j Apdf 1997 Rod Drop Testing 4

s Adions Based on Inemaplete RCCA Insertion Candition

(

s d '

c,ge,g..

i a

m g,

1. JimurtupUnit Case 1 All'

- Rasert1knsa a t 2.

No aM*ianal short tunn acoces l

4 g

3.

r--

' = resuks to theNRC 1.

Stenup Unit AE Immedsate Rassaitlimit E mM, 2.

Review data and evaluate seductag the,

1 Case 2 but

)

IP.rnuP interval pior e the and rod drop t

AllReviewhans met tout Evaluate revision ofshusdown

!I amargin caksdatiar= fr,'

within 2

~

i weeks abrstartup g

3.

hurucaseresolu so the NRC E Review 1hnitMmet, 1.

BriefNRC of asst issuhs and any planned Case 3 but

• • • '" N " 8"'t AIA safety Evalunionbmisy 2.

startup Unit 1.

Evatusse data and revise the Safety case 4 AE.tafety EvalumnonIAnitEmet Ede wWreactwcore i

2.

Infonn NRC I

• MMieria applies to Red Drop 'nme limiu and a single Cseegory of Staidown Margin limia.

?

l E

i o

1 i

c Page 2 of 2 g.d M M Els DHISKD17 kR:r5DrN LS*SO ET-E6

\\

l ST-HL-AE-5605 FileNo.: 003.03 10CFR50 i

U. S. Nuclear Regulatory C==i== ion Attention: Document ControlDesk Washington,DC 20555 4

SouthTexas Project Unit I and Unit 2 Docket No. STN 50-498 Rennits of Contml Rewi T =tino in Ra=nana, in NRC Bulletin 96-01 4

References:

1) NRC Bulletin 96-01 dated March 8,1996, " Control Rod Insertion Problems"

2) Im from T. H. Cloninger to the U. S. Regulatory Commission dated April 4,1996, " Response to Nuclear Regulatory Commission Bulletin %-01,"

(ST-HL-AE-5333) i Attached are the South Texas Project's results for:

the hot, fu11 flow rod drop testing in Unit I for end of Cycle 6, which was performed on January 25,1997 (Attachment 3);

i the Unit 2 end of Cycle 5 (hot, full flow) rod drop testing performed on February 8,1997 (At+-hmant 4);

the Unit 2 beainnina of Cycle 6 (cold) rod drop testing p.demed February 20, 1997 (A*-hm** 5); and the Unit 2 beginning of Cycle 6 (hot, full flow) rod drop testing performed on February 24,1997 (Attachment 6).

A core map is provided in A**h=M 1 to assist in understanding the test data provided. In

)

addition, Attachment 2 is provided to show the current Unit I and Unit 2 speciSc core design data.

An*hmant 7 shows the results of some fuel assembly drag testing that was performed prior to the start of Unit 2 refbeling outage in February 1997.

4 EwpWero epO496\\5605. Doc 3/1967 2:19 PM

~

4

. 3 I

. ST-HL-AE-5605 l

File No: 003.03 i,.<

Page 2 i

4 Based on the usults of the January 25,1997, testing in Unit 1, the South Texas Project will perform additional testing for both Units during the current cycles. Attachment 8 provides the control rod testing schedule for the current oors cycles for both Units (Unit 1 Cycle 7 and Unit 2 Cycle 6).

i f

A"eh==* 9 shows the chronological history of w,+p '=+ mgarding NRC l

Bulletin 96 01 and subsequent iesting.

j If you have any questions maarding this subject, please contact Mr. R. F. Dunn at j

(512) 972-7743 oc me at (512) 972-7795.

i D.A.Leamr

Director, NuclearFueland Analysis JMP/

A* c ' ests: 1. Core Map of Control Rod Locations (Ce=a to both Units)

2. Unit I and Unit 2 Core Design Data

3. Unit 1 Cycle 7, January 25,1997. Hot Rod Drop Test Results

4. Unit 2 February 8,1997 End of cycle 5, Hot Rod Drop Test Results

~

5. Unit 2 February 20,1997 Beginning of Cycle 6, Cold Rod Drop Test Results

6. Unit 2 February 24,1997_hai=iae of Cycle 6, Hot Rod Drop Test Results

7. Unit 2 Fuel Assembly Drag Test Results

8. Unit 1 Cycle 7 and Unit 2 Cycle 6 Rod Drop Testing Schedule

9. NRC Bulletin 96 01 Cwe-t-- ':+:+ Table EN. DOC 3/19&? 2:19FM

I Atwhment 1 l*

ST-HL-AE-5605 Page1of1 1

~

Care Map af Control Rod Imatiqns j

(Common to Both Units}

i

~

R P

N M

L K

J H

G F

E D

C 5

A i

1 l

1 l

j 2

SA B

C B

EA 4

3 SD SB SB SC 4

i e

M D

E D

u l

5 K

A A

E

)

i 8

B C

A C

B i

l 7

2 g

a C

E A

D A'

E C

e 88 SB i

i Io B

C A

C B

1 i

11 SD A

A SC i

12

$A D

SE D

SA i

i 13 SC SB SB SD 14 SA B

C B

SA 16 SA-Shutdown Bank A A-Control Bank A SB - Shutdown Bank B B - Control Bank B SC - Shutdown Bank C C-Control Bank C SD-Shutdown Bank D D-ControlBank D SE - Shutdown Bank E l

--,n m

a

- - ~ -

._._._m_

ST-HL.AE-5605 Page 1 of 2 Unh 1==A Unk1 Pawn hant-n Des =

l Unit 1 Cycle 7 FuelBursup Dats Core fiiiWD MJ a/U Core Puel B/U B/U Im noC EOC Im ID BGC _

BOC Cycle B/U

• 0.0 16A*

Cycle 5/U*

0.0 16A*

i ganwtw (ownwim townwrm fowD$mo SA A

I I

D2 0 04 26.4 1 37.8 E5 104 17.0 l 35.4 B 12 013 26.7 37.9 B Il 301 17.0 1 35.5

~

M-14 Gil 26.4 37.8 L il H35 17.0 35.5

__P-4 02) 26.4 37.7 L-5 IB6~ 16.9 35.4 i

_ B-4 G28 26.2 37.4 H4 H4$

17.7 36.6 i

D 14 G03 26.7 38.1 F4 M46 17.8 36.7 i

P-12 66iI~

25.9 37.4 H-10 H48 17.7 36.7 M2 G34 26.4 37.6 K4 H47 17J 36.6

~'

SB B

_O 3 N08 17.1 34.9 F2 M0

_ 0.0 20.2

+

C9 N05 17.0 34.9 S 10 M5 0.0 20.2

~

J-13 H12 17.1

$4.9 K-14 342 0.0 20.2 N7 H09 16.9

_ 34.8 A

J41 0.0 20.2 i

C7 H10 17.1 34.9 34 J46 0.0 20.1 i.

O 13

'R07 17.1 35.0 F-14 4 M3 03 20.1 N-9 HI1 17.1 35.0 P-10 M4 0.0 20.1

~I H06 16.9 34.8 K2 J38 0.0 20.1 J

3 i

~

8C C

l E3 H13 17.7 35.8 H2 757 17.2 34.0

~~d~11 H28 17.6 35.7 B4 T59 17.3 34 6~

~

L 13 Ifl8 17.6 35.7 H-14 T60 17.3 34.0

~

~

i N-5 H24 17.5 35.6 P4 T58 17,.,3_

34.0

~

SD F-6 H32 16.9 35.0 C5 H23 17.7 35.7 F 10 H29 16.8

~~ T4 3

E 13 His 17.7 35.7 K 10 806 17.0 35.1 N.ll H16 17.7 35.8 K4 H33 16.9 3$.0 L3 E23 17.8 35.8 D

i SE D4 C34 21.5 37.6 H4 Hol 14.6 32.7 M-12 Cid 21.9 38.0 i

D4 H02 14.$

32.6 D 12 C24 21.7 3T8 H-12 H04 14.6 32.7 M4 C16 2T8~l 37.9 l

M4 H03 14.6 32.7 H4 i C62 22.0 l 36.3

~

l

• EOC burnup assumes no coastdown operations j

Unit 1 Cycle 7 Rodded Fuel Asseeably Data (14 foot actWe fuel and le grids)

"C","O"hsme Snailed Aassablies "7","H","r % V5H Assemblies laconst st-f=~s gA=

srds, areonhan and snds a

Zirconnan gidde tubes EW8 saids nabas

{

saunless seselgrid slaves Zircontam arid sleeves outes adiirf5 (above dashpor) = 0.450 inches outes tube to (above anshpoi) = 0.44f"lisiEs-Ciuds tube ID (dashpot) = 0.397 inches Guide tube ID (deshpot) = 0.397 loches i

r

,r

l l*.

Awu 2 ST-HL-AE-5605 Page 2of 2 Unit 1==,1 Unit 2 (be P ='=. E0 i

Unit 2 Cycle 6 FeelBurmap Data e

j Core PuolID B/U S/U Core Fuel 8/U WU i

Loc a0C EOC' Lac ID BOC EOC*

i Cycle n/U-0.0 20.2 Cycle WU-of 20.2 WWD*dTLD #wnsmo swasmo Mwommo SA A

T2 NI7 14.1 23.7 E5 L V24 0.0 25.4 3

3-12 N51 14.1 23.7 E 11 V13 05 0 25.4 i

M 14 N29 14.1 23.7 L 11 V14 0.0 25.4 i

P4 N32 14.1 23.7 L5 V18 0.0 25.4 B4 N19 14.1 23.7 M4 N40 13.8 31.9 l

D 14 N26 14.1 23.7 F-8 N06 13.8 31.9 1

P 12 N!!

14.1 23.7 H-10 NO2 13.8 31.9 i

M-2 N45 14.1 e 23.7 K4 N33 13.8 31.9

$8 B

G3 V16 0.0 26.3 P2 V68 0.0 23.6 l

C9 Vit 0.0 26.3 B-10 V73 0.0 23.6

~ Fi3,

V27 0.0 263 K-14 V70 0.0 1

23.6

~

N-7 V28 0.0 26.3 P4 V69 0.0 23.6 C7 Y22 0.0 26.3 B4 V74 0.0 23.6

~

~

0 13 V26 0.0 26.3 F 14 V71 0.0 23.6

~

N9 Vl9 0.0 '

26.3 P-10 V72 0.0 23.6 J-3 V11 0.0 26.3 K-2 V66 0.0 23.6

~

SC C

~

E3 V82 0.0 1 25.6 H2 V54 !

0.0 24.5 C Il

~95T~

0.0 25.6 B8 V64 0.0 24.5 L 13 V77 0.0

~~E~6 H-14 V59 0.0 24.5 N5 V84 0.0 25.6 P4 V$3 0.0 24.5 SD F4 N21 11.5 29.9

~

C-5 1 V78 0.0 25.6 F 10 N24 11.5 29.9 ~

~

E-13 V89 0.0 25.6 KT0 N30 11.5 29.9 N Il V85 0.0 25.6 K4 N25 l 11.5 29.9

~~

~

L-3 V79 0.0 25.6 D

SE D.4 N08 13.6 30.8 H-4 7 32 0.0 25.9 M 12 N01 13.6 30.8 D4 V40 0.0 25.9 D 12 N38 13.6 30.8

~~

H 12 V34 0.0 25.9 M-4 N58 13.6 30.8 M4 V29 0.0 25.9 H4 N3T I1.7 30.6

• EOC burnup assuines no coastdown operations Unit 2 Cycle 6 Rodded Feel Assoasbty Data (14 foot actin feel and 14 grids) 21 x"N" Region $saadant Aseanblies 36 x "V" ** V5H Assemblies

~Eljirids Inoosel topbaam grids, zirooniwa said arids~

z6i== suide tubes Zirconkun suide tubes sininises soil, grid slems Elroonhan arid elems Guide sube ID(above C)-0.450 inches Guide tube ID(abm dashpot)- 0.442 "-

omde tube ID(dashpot)= 0.39 finches W tube ID (**) = 0397 inches

~~~

i A*-he 3 ST-HL-AE 5605 i :

Page1 of 1 1

Egr 1 Ovele 7 hana v M 1997 Nat hd E.

Tant h -ha Rod drop time testing was p L=ed on all 57 comrol rods. The plant was in Mode 3 with the Reactor Coolant Syste.m %4dre greater than 561*F and four nmetor coolant pumps running. Two rods stopped at 6 steps from rod bott0nl based on Digital Rod Position 1

i i

Indication (C9 and K8)*, and all other rods fhlly inserted. These results represent the first observed incomplete rod insertion (iRI)in V5H msemblies at STP. In addition, fuel benup j

for the two IRI assemblies was substantially lower than pseviously observed. The average rod drop time was comparable to previous testing p.fm 44 this cycle, however, a notable dashpot omry time increase of 0.1 see was hr4 at core location H 10. Test results mariefied all Technical Speci6 cation and safety evaluation limits during the test.

l Core FuelID B/U DE Recoils Core I%elID B/U DE Recoils i

the 1/25/97 Time lac 1/25/97 Tiene j

(oWDMI9 S

.._,,. ec)

(OWDSffU)

@se i

Cycle av -

8.29 Cyeie a'u -

s.29 j

SA

~

A D2 0 04 32.0 1.587 3

E5 H34 26.4 1.594 2

i T12 G13 32.2 1.597 3

E Il H31 26.5 1.5fi~

l M-14 0 11 32.0 1.616 3

L ll H35 26.5 1.580 1

P-4 O2l 32.0 1.587 3

L5 DD0 26.4 1.567 2

~~~

B4 028 31.7 1.594 4

H4 H45 27.4 1.647 1

~

D 14 0 03 32.3 1.601 3

F-8 H46 27.5 1.652 0

~~

~

P-12 G09 31.C 17597 3

F10 H48 27.4 314 1 ~

{

M 2 1 034 31.9 1.621 3

K 8*

H47 27.4 1 1.646

'O l

2 B

O3 H08 26.2 1.598 3

F2 MO 10.0 1.590 3

I C 9' H05 26.i~

1.634 0

B 10 M5 10.0 1.609 2

~

J 13 H12 26.2 1.604 2

K 14 22 10.0 17604 3

i N-7 H09 26.0 1.620 2

i P4 MI 10.0 1.574 4

~

~~

g$

~III0 26.2 1.698,

O B4 M6 9.9

__1.604 2

G 13_ _H07 26.2 1.616_

2 F 14 J43 10.0 1.574 1.557 T_ 3 i

N-9 H11 26.3 1.567 0

P 10 J44 10.0 3

33 H06 26.1 1.584 2

K2 J38 9.9 1.602 3

l~SC C

E3 H13 26.7 1.603 4

H2 f57 25.6 1.613 3

l C Il li28 26.6 1.632 2

84 T59 25.6 1.614 1

L 13 HI8 26.7 IJ82 3

H-14 T60 25.7 1.630 2

N5 H24 26.6 1.618 3

i P-8 T5s 25.7 1.

I C-5 H23 26.7 1.629 2

~f-10 H29 26.1 1.614 1

E 13

~His 26.7 1.584 3

K 10 H36 26.3 1.594 2

N-Il Hl6 26.8 1.596

.2 K4 H33 26.2 1.613 3~

L-3 II25 26.4 1.618 3

D SE D4 C34 29.6 1.570 2

~

H-4 H01 23.9 1.5:s 3

M 12 C14 30.0 1.571 2

D.8 H02 23.8 1J70 1

D 12 C24 29.8 1.598 1

~

H 12 H04 23.9 1.601 2

M-4 C16 29.9 1.5'Il 2

{

M-8 H03 23.9 1.568 1

H4 C62 29.1 1.545 1

l 1

j '.

p Attachmane 4 1

{.,

ST-HL-AE-5605 Page1 of 1 i

l

. Unit 2 Fahemm7 1997 F=A af Orch E. Lt D=A En,; Tagt Dm=b R

l j

Rod drop time testing was i.e.forsned on all 57 control rods. The plant was in Mode 3 with j

the Reactor Coolant System tamparature greater than 561'F and four reactor coolant panps running. Four mods stopped at 6 steps Aom rod bottosa based on Digital Rod Position Intlieneirm (D-8, E-11, F-6, and H-8)*, one sod stopped at 12 steps (F-10)", and all other tods fully inserted. These results represent the first IRI condition observed in Unit 2. the last rod drop test was on January 11, 1996, a cycle burnup delta of w :=*1y 13.7 OWDMIV. The average rod drop time was slightly higher than previous testing i Wed this cycle, and the test data showed notable dashpot entry time increases (9) of 0.1 see and 0.25 see at core locations H-6 and M-4, sospectively. Test results==tiefid all Taake=1 5;,eGe.'on and safety evaluation limits during the test.

Cort PaollD B/U DE Rooons Core Fuel!D B/U DE Recoils I

Loc 2/s/97 Time I.ec 2/8/97 Tinw townwrU) gee) towensTU) ges)

Cycle b/U~

16.0 Cycle.B/U ~

16.0 SA A

D-2 S35 44.2

, 1.$85 1

E-5 Sl9 40.4 1.567 0

B.12 Sol 44.2 1.i9fI 1 E-11*

S12

~

E14 542 44.2 1.603 2

L-Il 80$ _ _ 40.4 1.$69 0

i 40.4 1.$79 0

~T95~

2 1-$

S06 40.4 1.627 0

P4

$61 44.2 1

B4

$59 44.3 1.590 1

H4 $

T53 39.9 1.770 0

i D.14

$64 i

44.3 1.596 I

F4 TT5 39.9 1479 0

j P 12 549 44.3 1.582 2

H 10 TS6 39.9 1.637 0

42

$63 44.3 T5T3 i

K8 TS4 39.9 1.582 2

sa a

O-3 126 39.2 1.613

'2 f2 U40 19.4 1A06 3

C9 T32 39.2 1.663 i

B 10 U37 19.4 1400 4

J 13 f31 39.2 1.603 2

K 14 U44 19.4 1373,

3

~~

N7 728 39.2 1.ft9 2

P4 U41 19.4 1.684 2

C7 fl7 39.1 1.607 I

84 U42 19.4 1.573 4

O 13 T30 39.1 1.594 2

F 14 U39 19.4 1401 2

~~

N9 T20 39.1 1.569

~~ 2 F~10 U43 19.4 1.577 4

J3 T21 39.1 1.601 2

K-2 U38 19.4.

1.579 2

SC -

C B3 U21 39.4 1.63I '

1 H-2 U17 32.0 1422 3

C 11 U35 39.4 1.593 2

34 U19 32.0 1.634 2

1 13 U26 39.4 1.615 2

H 14 U16 32.0 1478 3

~

N$

U30 39.4 1434 2

P4 Uls 32.0 1.$F 3

$D F.4*

S21 39.8 1.$91 0

C5 U31 39.4 1.612 3

F-30**

SIS

$9.8 1.$74 0

E 13 053 39.4 l 1 A13 2

K 10

$23 39.8 1.547 0

N 11 U24 39.4 IA08 i

K4 822 29.8 1.618 i

L3 U33 39.4 1440 3

D SE D4 870 49.9 1401 1

H4 572

$2.7 1.$74 1

2 12 S$4 49.9 1.591 1

D 4*

S$2

$2.7 1.T7$

0 D 12

$30 49.9 1.578 0

~

H 12 S$6 32.7 1.$72 1

M4$

$34 49.9 1.831 0

~

M4

$67

$2.7

! l 446 0

i F4*

m37 47.2 17610 0

i d

t A~h-at 5 ST.HL-AE-5605 Page1ofI o

Unit 2 Fahr =.w in.1997 H=s.. af C.a & tsu ha D. 9 est D M:

T 4

Rod drop time testing was performed on all 57 control rods. The plant was in Mode 6 with the Reactor Coolant System tamperstme approximately 93*F, no stector coolant p running, and the Ranctor Coolant System water level at the vessel flange. All rods i

inserted to rod bottom. Rod drop tinnes wuz comparable to last cycle's tasting

' owed at this condition. Test results satis 6ed all Technical Speci6 cation and safety evaluation limits during the test.

1 i

i Core

FuelID, B/U DE

• Ma Core halID R/U DE Recods 1mc 2/20/97

'!1sne 14c 2/2W97 Tlaw i

(OWDeffU) Oes) l Cycle IVU ~

0.0 6i-wi4IU) Geo)

Cycle B/U-+

0.0 l

SA A

D2 Nil 14.1 1.071 S

E$

V24 0.0 1.061 B 12 N51 14.1 1.056 E 11 V13 0.0 1.063_.

M-14 N29 14.1 1.060 bil Vid 0.0 1.0$9 5

[

P-4 N32 14.1 1.069 4

b$

Vis 0.0 1.061 5

i B4 N19 14.1 1.064 5

H6 N40 13.8 1.070 4

j ID 14 N26 14.1 1.0$4 4

F-8 N06 13.8 1.056 i

P 12 N11 14.1 1.067 H 10 N02 13.8 1.056 4

M-2 N4$

14.1 1.070' 4

_K-8 N33 13.8 1.061 4

SB B,

t 03 V16 0.0 1.062 5

F-2 V68 1 0.0 1.0$3 5

i C9 V17 0.0 1.0$6 4

B 10 V73 0.0 1.0$7 I

J 13 927 0.0 1.059 I 5 K 14 V70 0.0 1.056 N7 V28 0.0 1.063 P6 V6) 0.0 1.056 C-7 V22 0.0 1.0$9 B-6 V7T 0.0 1.068 4

~

l O-13 V26 0.0 1.0$8 c

F-14 V71 0.0 1.064 5

}

N-9 Y19 0.0 1.06$

5 P 10 V72 0.0 1.064 4

}

33 i Vi1 0.0 1.067 4

K2 V66 0.0 1.061 4

SC C

_ E-3 V82 0.0 1.052 H2 V34 0.0 1.062 j

C.11 Yt3 0.0 1.053 B-8 V64 0.0 1.068 5

i 1-13 V77 0.0 1.0$8 5

H-14 VS9 0.0 1.059

}

N-5 V84 0.0 1.0$3 5

P-8 Y$3 0.0 1.058 4

~

SD F6 N21 11.5 1.059 4

C5 V78 0.0 1.065 F 10 N24 11.$

1.059 3

E 13 V89 0.0 1.063 K 10 N30 11.$

1.068 4

)

N 11 V85 0.0 1.069 6

K6 N25 11.5 1.060 4

1 13 V79 0.0 1.068 D

l SE D4 Not 13.6 1.069 4

l H4 V32 0.0 1.058 M-12 No1 13.6 1.061 5

l D8,

V40 0.0 1.054 D 12 N38 13.6 1.062 1 4_

3 H-12 V34 0.0 1.0$9 4

M.4 NS8 13.6 1.0$8 i i

M8J V29 0.0 1.06$

5 H-8 N37 11.7 1.069 t 4

r 1

I I

I 4

i* -

l.

ST ILAE-5605 Page1of1 Unk 2 Febr==w 1.1 1997 E '_.mtme af Ovele 6. he Dad D=.: Tant Da -he Rod drop time testing was performed on all 57 control rods. The plant was in Mode 3 with the Ranctor Coolant Sy8 tem temperature greater than 561'F and four reactor coolant pumps 3

i running. A11 ods fully inserted to rod haam Rod drop times were comparable to last cycle's testing performed at this condition. Test results anti =W all Technical SMMon j

and safety evaluation limits charing the test.

Ces FuelID B/U DE REoils Core FuelID B/U DE Recoils i

I.mc 2/2447 Tune lac 2/24 S 7 Tune gmostrU) tommrru)

Cycle B/U-*

0.0 Cytle b/U-+

0.0 u

i IA A

D.2 N17 14.1 1.624 4

E-5 Y24 0.0 1.$72 4

j D-12 NSI 14.1 1.614 5

E. li _ __ _ V13 0.0 1.567 4

1 M 14 N29 14.1 1.661 5

1-11 Vi4 1 0.0 1.593 6

i P4 N32 14.1 1.605 5

L5 Vit 0.0 1.588 5

~

{

S4 N19 14.1 1.632 H4 N40 13.8 1.6i3 4

~

D 14 N26 14.1 1.638 F8 i N06 13.8 1J93 4

P-12 N11 14.1 1.616 H 10 N02 13.8 1.$$$

5

~

l 3

N45 14.1 1 1.617 K-8 N33 13.8 1.$66 5

M

~

sb i

a i

O3 V16 0.0 IJ94

, 4 F2 V68 0.0 7.I90 3

C9 V17 0.0 1.564 4

B-10 V73 0.0 1.589 5

i 3-13 V27 0.0 1.584 5

K 14 V70 0.0 1.$97

~

N7 Y28 0.0 1.56T 6

PJ V69 0.0 1.619 C-7 V22 0.0 1.5$2 3

84 V74

,_ 0.0

' l.$47 4

G 13 V26 0.0 1.$27 4

F-14 V71 0.0 IJ97 5

_N9 Vl9 0.0 1.$70 5

P 10 Yb 0.0

, l.$81 5

' I J3 Vil 0.0 1.$83 4

i K2 V66 0.0 1.591 5

SC C

E3 V82 0.0 1.592 5

H-2 V54 0.0 1.$95' 5

C-Il V83 0.0 1.568 5

B-8 V64 0.0 1.579 1 $

l-13 V77 0.0 1.$87 5

H 14 V59 0.0 1.571i

$~

N$

V84 0.0 1.$85 4

P8 V53 0.0 1.572 1 5

~TD F4 N21

!!.5 1.571 4

C5 V78 0.0 1.589 5

F-10 N24 11.5 1.$65 4

E 13 V89 0.0 1.595 4

K-10 N30 11.5 1.554 5

N 11 V85 0.0 1.569 5

K4 N25 IIJ 1.563 5

L3 V79 0.0 1.624 5

iT

~

SE D4 N08 13.6 1.619 H-4 V32 0.0 IJ58 M-12 N01 13.6 1.613 5

D8 V40 0.0 1.580 D 12 N38 13 1 1.$17 5

H 12 v34 0.0 1.567 M.4 N58 13.6 1.$94 M-8 Y29 0.0 1.S$8 5

H8 N37 11.7 1.609 e

~

l Aumchment 7 l

ST-HI-AF-5605 Page1of1 tima 2 paal A-uv n= Tame n-te.

l Drag testing of 26 Unit 2 Cycle 6 rodded fhol assemblies was perfonned in the Spent Fuel t

Pool prior to the 2RE05 refbel outage core reload. These assemblies were selected because i

they had contained old hafnium control rods, and during removal of these hafbium rods, an i

overload condition was initially observed on the handling tool. To ensure the overload condition would not affect controhod insertion is the new core, drag testing was perfmned to evaluate thimble tube drag forces. Drag testing was s'

.ed using a dummy control rod 3

w with the contml rod being inserted and withdrawn in the host anaembly while mag drag data from a calibrated load cell. For the assemblies below, there was minimmt drag above the dashpot - thimble tube drag forces ranged from 3 to 6 lbf above the 4=N--t.Only the average dashpot drag values are listed below. The criteria used for excessive drag in the j

dashpot was 100 lbs, and is based on fuel vendor mmandatians 4

i

_Unk 2 Thimble Tabe Drag Testias la 5sent Fuel Fool Fool Assembly AveruseDashpot Dres Force Ob6 i

i.

N01 18.3 N02

_10.$

N05 16.5 NC 17.5 j

NOS,

24.3 l

N11 15 j

N17 1

15.$

N19 18.$

N21 17.3

~

N24 14.s N25 21.3 N26 19 i

N29 25.8

N36, 17 i

N32 16 N33 15.8 N34 20.5 N36 19 N37 17.5 i

N3:

17J N40 17.5 N43 15.5 N45 17.5

~

N$1 18J NTf 17 Vil*

13 3

• NewV5H assembly as reference 3

4 i

s e <

v.-

-,r y-_

yv

i'.

/

Anachment g l *.'

g ST-HL-AE-5605 Page 1 of 2 1

Unk 1 Ovele 7==d ifnk 2 Ovele 6 hd tre.; T- '* - Wule Based upon acent rod drop test data which showed that incomplete rod insertion (IlU) can j

occur in XL V5H fbel at lower burnups than XL standard fuel, STP has established nominal design bel assembly burnup limits to mitigate IRI. 'Ibese naminal design burnup limits are

-25 OWD/MTU for XL V5H fbel and 30 GWDMIU for XL #andard fuel, applicable to j

rodded core locations. Based on STP rod drop test data, sodded fbel assemblies With burnups

--d% these limits may be subject to the IRI condition. Both Unit 1 Cycle 7 and Unit 2 i

Cycle 6 have rodded fuel assemblies that will exceed these burnup limits prior to the and of l

cycle. Until an analytical tool is developed to predict IRI behavior in fbel assemblies, or other corrective actions, e.g. fbal design 4=- p, are in place to prevent IRI, i b..ance of l

rod drop testing to verify safety analysis assumptions is prudent. A testing schedule has been designed based upon a nominal 2.5 OWDMIU cycle burnup interval between tests, and is i

conservatively initiated based upon exceeding the burnup limits in the lead (highest burnup) rodded assembly for the applicable fuel type. Also, should an outage of suf5cient duration 3

occur in Unit 1 or Unit 2 during the current fbel cycles, rod drop testing will be performed for all control rods when at least 1.25 GWD/MTU cycle burnup has been accumulated since the j

last rod drop testperformance.

r When assigning a calandar date to a cycle burnup, an assumption must be made about the

)

operating history up to that point in time. Therefore, listed test dates and associated cycle

{

burnups may need to be adjusted based upon actual operating history, or plant shutdowns, in order to meet the nominal 2.5 GWD/MTU cycle burnup interval. Other factors considered in developing the test schedule are keeping the intervals about equal, reducing nanaca==ry j

generation of =dMve waste water, and avoiding shutdowns during peak electrical dammad

{

periods or national holidays, e.g., July 4,1997.

j Unit 1 Test Schedule j

The projected Unit 1 Cycle 7 test schedule consists of three rod drop tests fbr the remainder j

of the cycle. 'Ibe projected test achedule is summarized in the table below, with the January i

25,1997 rod drop test shown fbr -:-3'r i

Test Date Cycle Burmsp Imad Rodded F/A Barnap Cycle Burmsp Differomoe

{

(GWDWTU)

(GWDMTU)

(GWD/MTU) i XL V5H XL Sundard j

1/25 M 8.3 27.5 32J 8.3 l

4/12.9 7 11.0 30.6 34.2 2.7 i

6/2&97 13.8 33.7 36.2 2.s 3

9/13 M 16.3 34.8 38.1 2.7 I

l i

i i

i

(.

p l

ST-HL-AE-5605 Page 2 of 2 l.'

Unit 1 Cvele 7 and Unit 2 Cvele 6 Rnd Dmn Teelne hbAnle i.

i Unit 2 Test Schedule

).

l The projected Unit 2 test schedule is conservetively initiated based upon ~9ng 30 GWD/MTU in the lead XL STD fact assembly hennae the XL STD land fhel assembly I

exceeds the burunp limit prior to the lead XL VSH assembly. The projected test schedule is summarized in the table below.

1 i

Test Date Cycle Barsup Land Rodded F/A Barsap Cycle Burmap Differseee (OWDMTU)

(GWDMTU)

(OWDMTU) f

~

XLV5H XL Standard i

7/25/98 18.4 24.1 30.3 1

j 10/3 # 8 20.9 27.2 32.6 2.5 i

s l

Testing Plan Justineation j

This testing plan is acceptable based on the following:

Rod drop test data from Unit I and Unit 2 indicate the IRI condition propagates slowly j

with core bumup, The current safety analysis provides conservative, bounding shutdown margin l

calculations for hypothetical stuck rod configurations beyond what has been experienced at the South Texas Project, and I

Conservative unit restart criteria will be in place for planned rod drop testing to prescribe e

guidance for additional actions, which may include reducing the burnup interval between rod drop tests.

,r-

.y e

r y

N

- t+ a m

Anachment 9 i

ST-HL AE-5605 Page 1 of 1 NRC Belletin M ^1 Cc.;. - --de -* Table DATE TO FROM SUBJECT La.t 1ER #

Memh 8,1996 AllLicensees NRC NRC Bulletin 4 01

• Control Rod Insenion Problems"

~ April 4,1996 NRC STP Response to NRC Bulletin 96 ST-WAE-5333 (T.H. N ia!=)

ControlRodinsanion Problems June 5,1996 STP NRC Public Meeting to Dancuss E-- =pW-ControlRod lasertion July 3,1996 NRC STP Results of Control Rod Testing in ST-LAE.5408 (D. A.14 azar)

Response to NRC Bulleta 96 01 November 27,1996 NRC STP Results of Fuel A bly Testing in ST-Hl.-AE-5516 (D. A.Leazar) 8-p To NRC Bulletin 96-01 NRC STP Results of Control Rod Testing in ST-WAE 5605 (D. A.Imzar)

Response ToNitC Bulletin 96 01 (This Letter)

g p

gg'{ "- "g }

g Cecyhtet.1 FL to Cvericw InFarnatian

{

Tks Mac se esta4:47 1997 3.30 -

y...: in or cvcar le

~

2 j

s.4s -

t 1

1 i

l 4

8/W(?

1. e4 -

i 3

f.

f 4

i e. e2 -

O '"

~

A-W 11IlitIIi ilIi1ii4I ieiltilli aliiilIii iiiiy1rl I41IillII' j

e See lese 1500 ames 2S89 30ee U"I*

A Tisee (ns3 N8 C7 C7 Post-it' Fax Note 7671 mm $/p/ p'af > 6

" N e w 6 4 u = 64 % 4 " @416 M

prop:

1 i

"" Mitc

" M Tarr46 % >.

rtto:

c7stsva.ana crosssi. ann m,

g m,g l' e/ 4 s 56G i

' h M e sanest :

asse

ine, 98 C*

9000 Threundt 3899 2344 Tzeep :

5s7.e ses F 565.0 see F Preost-3235.s PSIC 2211.8 PSIG rt ' Rate :

See.e M

100.0 M

Cw21s t 7

7

f1AR-20-1997 ' 09:58 STP HL&P IL) CLEAR EtG 728081 P.02/06 Graphical File Overlav Internatten Thu Mar 2e 08:19856 1997 3.90 -

l.

I

~

( % vbu I$J% OW & "W 3.31 -

l

\\

~

r 1.54 -

t/z1/97 8

~

\\

s s.77 -

t 3

\\

l

=

e.ee

,,ig,,,

S See 18ee 1998 2988 3500 3ese Unitt TN h)

Codi C9 CS Dr:Pt i

1 Tila 1 C981971.RDA C996961.RDA DA;hP:ti 1634 157e Tersundi E

221e 7:ny:

567.e Des F 565.8 Dew F Preso3 2e35.e PSIC 2211.e PSIC T1 Ratet 180.3 X

ise.e M

Cue 10 t 7

7

i MAR-20-199'/ 09:58 STP HLEP NUCLEAR ENG 9 28081 P.03/06 l

l Craphical Tile Dwerlau Internation l

Thu Nar 30 88345835 1997 l

MWp 4 DP bCLE-

~

1/25/f7 1

i j,

~

I l

3.53 -

i e

l 1.75 -

2 B

L e.se -

b, y,,s,3,,,,,,,.

A e.se r

t 500 itet 1566 Stee 3589 3086 l

i

1. "I*8 1

7t ne his )

Cod:

34 54 66Md A

EAtE Ft1oa 3481971.3DA 9406941.RDA sa:hp;ti 1594 15e9 Teresand 2163 2162 T:ne:

567.5 Dew F 565.8 Des r Preso:

RaSo.e PeIC Se11.e PSIG l

F1 Sate Ate.e x

lee.e X

Cv310 :

7 7

i

t1AR-20-1997 09:58 STP HLEP NUCLEAR EtG 9728081 P.04/06 Craphical File Overlav Inf ormation Thu Mae se 0s:4a:39 1997 3.39 -

Ves/n

~

/ % /alid/UC b7 GsCLd" t

3.s4 -

l g

o.

k e.es -

~ /

r

]

bA A>.

I 8*88-iiainsili ilisilisi signistii i::::::::

i a l ly Wrvil l i i I l l o

se e le se isne sese asne sese Unit:

1 Tim (m) 610gO (DM~t~M>L.bM d ~ \\Q,AC.9 Dropt i

1 Fi to s Pse1971.RDA P6e6961.RDA pa:hyst:

1574 1564 Tereunds ages see7 Toser s as7.a pas r sas.e mes r i

l Presos mass.s Ps:c am31.s Ps:c F1 sate:

188.8 M

19e.G W

Custot 7

7

t1AR-20-1997 09859 STP HLEP t4JCLEAR Et4G 9728081 P.05/06 Craphical Tale Overlag Internatten TM Mar as 38831884 1997 2.96 -

O, lWi% C'"CVCur P

. ~

s/r5/97 l

l l

I 2.22 -

i L

i 1

i

1. 4. -

\\

S.74 -

~

I '"

eIiIllIii 14itil6II illa 11644 tillIiii6 eii4yift i I 616 t i l l l 8

588 1988 1568 2988 25ee 2006 Uniti 1

Tine Cns)

Cod:

MS MS Drept i

1 FiloI Nas1971.RDA Nee 6961.RDA Ba%p;ti 1646 1638 Throundt 2541 3350 Tenyt 967.9 Des F 565.8 Der F Preso8 3235.O PSIC 2311.9 PSIC Ft De,tei 189.5 A

188.8

• A cv31ot 7

7

vt;X-24PW5X bacea

'SwnG99EL90FXTRE 7724 6 -4 P.LG/06 Cr:phiset rito overtej Intcenatt en Thu Mar as se329:2s 1997

3. se -

hMuth fa O F bC L.4

~

a. as -

pg

\\

1.4e -

s.7e -

iiiIVialb E'EE iiii6 I ii l

iiieiiIii 414ii4433 Iiai4aiii ii43 54 iiI e

see Lees 1see mees asse seee U"I&I A

fine (ns>

Cod:

To r8 Dece:

1 1

F1to8 FeS1971.RDA Fee 6961.RDA DashPeti 1883 1611 Teresand B 2734 Bes?

T:ne:

367.e Des Y e68.e Des T Press 3235.e PeIC 2211.8 PSIC rt Ibte:

138.s M

Lee.s M

Cucts :

7 7

vnva o nc L