ML17265A230

Forwards Response to RAI Re Review of Request for Amend Dtd 970929 for TS Related to Main Steam Line Isolation Signal Setpoints

ML17265A230
Person / Time
Site:	Ginna
Issue date:	04/17/1998
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9804220178
Download: ML17265A230 (24)

Text

CATEGORY 1 1

( ~W~>c P REGULAT RY INFORMATION DISTRIBUTIO SYSTEM (RIDS)

ACCESSION NBR:9804220178 DOC.DATE: 98/04/17 NOTARIZED: YES DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAMF~ AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas 6 Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S.

SUBJECT:

Forwards response to RAI re review of request for amend dtd 970929 for TS related to main steam line isolation signal setpoints.

DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR SIZE: A ENCL TITLE: OR Submittal: General Distribution T NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72) . 05000244 E RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-1 LA 1 1 PD1-1 PD 1 1 VISSING,G. 1 1 INTE . FILE CENTER 1 1 NRR/DE/ECGB/A 1 1 1 1 NRR/DRCH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D

0 C

N NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE, WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL 12

I%

Ik

AND ROCHESTER GAS AND EIECIIC CORPORATION ~ 89 EASTAVENIJE, ROCHESTER, N. Y Id6rI9-0001 ARFA CODE 716 546-27Ã ROBERT C. MECREDY Vice President Nuclear Operations April 17, 1998 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555

Subject:

Response to Request for Additional Information (RAg Rochester Gas & Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244

Reference:

Letter from G.S. Vissing, NRC, to R.C. Mecredy, RG&E,

Subject:

Request for Additional Information - Review ofRequest for Amendment Dated September 29, 1997 - Change to the Technical Spectftcation Related to the Main Steam Line Isolation Signal Setpoints P'AC No. M99702), dated April 3, 1998.

Dear Mr. Vissing:

Enclosed please find a response to the referenced RAI. Please contact us if we may be of any further assistance.

Very ly yours, Robert C. Mecred Subscribed and sworn to before me on this 17th day of April 1998.

Notary Public DEBORAH A3'IPERNl Notary Public m the State of New York ONTARIO COUNTY MDF>961 Commtsston Expires Nov. 23, 19.+5, Attachment %xeo 9804220%78 9804%7 PDR ADOCK 05000244, P PDRg

E xc: Mr. Guy S. Vissing (Mail Stop 14B2)

Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector Mr. F. William Valentino, President New York State Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399

Res ne RAI fA ril 1 You stated in the February 6, 1998 letter that LOF7ZAN code was used to reanalyze steam line break events using the revised values (i.e., allowable value and setpoint).

Please provide the version of the code used in this amendment. Has this code and version been approved by the NRC (give reference to NRC approved Westinghouse topical report)?

The NRC approved Westinghouse topical report for LOFTRAN is:

a. WCAP-7907-P-A, "LOFTRAN Code Description," April 1984

b. WCAP-7907-A, "LOFTRAN Code Description," April 1984 Version 12.00 of LOFTRAN was used by RG&E which is the same version used by Westinghouse to perform the RG&E analyses documented in the Ginna Station UFSAR.

Please provide the results ofyour reanalysis.

The analysis performed by RG&E was for a 0.66E6 ibm/hr steam break in one steam generator. This case was compared to the bounding HZP Case 5-0 described in UFSAR Section 15.1.6.3. As stated in the UFSAR, the criterion for Case 5-0 is that the reactivity insertion rate should be bounded by the rate'esulting from a rod withdrawal from subcriticality.

Attached Figures 1 through 7 represent parameters from Case 5-0. Figures 8 through 14 represent parameters from the 0.66E6 ibm/hr steam line break in one steam generator described in the February 6, 1998 RG&E letter (hereafter referred to as Case SLB). A comparison of the parameters shows:

ao Resulting nuclear power is less for Case SLB;

b. Resulting RCS temperature reduction is less for Case SLB; C. Resulting pressurizer pressure reduction is less for Case SLB;

d. Resulting steam generator pressure reduction is less for Case SLB;

e. Steam generator mass trends illustrate the difference between a feedwater malfunction and a steam break; Total reactivity insertion is less for Case SLB but occurs over a longer time frame; and g The rate of reactivity insertion is less for Case SLB.

In summary, the parameters indicate that the Case SLB is less severe than Case 5-0 and that the limiting criteria with respect to the reactivity insertion rate is less than that for Case 5-0. Therefore, UFSAR Case 5-0 remains bounding.

UFSAR indicates that the reactor control system is designed to accommodate a 10% step change or 5% ramp. increases... without a reactor trip in the range of 12.8% to 100%

reactor power. However, you stated in the September 29, 1997 letter that a reactor trip would not occur in the range of 15% to 100% reactor power. Please clarify.

The UFSAR refers to permissive P-2 which allows automatic rod withdrawal once first stage pressure reaches an equivalent 12.8% reactor power. During plant startups, the rod control system is operated in manual with the operators switching to automatic rod control at some point above 12.8%. Similarly, during shutdowns, the control rods are switched to manual before reaching this 12.8% value. The September 29, 1997 text was intended to acknowledge that the operators are not necessarily performing the switchover to automatic rod control at exactly 12.8%, but at some point above this. Specifically, the NIS is designed to accommodate a 10% step change when rods are in automatic.

Figure 1 QNCLR B.eese 8 '848 8~ 8838 C

0 I

0 I

%J I

3 0

L I

0 0 8~ 8828 z

8~ Beie 4 32E-86 e.e see. 8 2ee. 8 388 ~ 8 4ee. 8 688 ~ 8 See. e 788 ~ 8 TINE (SEC)

CASE 6 0 HZP Both ARVa and Soth MFRVa

Figure 2 TAVG 668 ~ 8 6ee. e 46e. e 4ee. 8 368+ 8 3ee. e ase. e Bee ~ 8 e.e see. e aee. 8 388 ~ 8 4ee. e see. e 688. e 788 ~ 8 TINE (SEC)

CASE 6 0 HZP Eath ARVe end Bath MFRVe

Figure 3 PRo P a4ee.e 2288 ~ 8 aeee.e csee.e csee.e p 1488 ~ 8 0

3 N

face.e N

R 0.

1888 ~ 8 see. 8 see. e 4ee. e aee. e e.e 188 ~ 8 aee. 8 388 ~ 8 4ee. e Bee. e wee. e TIME (SEC)

CASE 6 0 HZP Both ARVs and Both MFRVe

Figure 4 PS PS mace.e xeee.e see.e see.e see.e see. e Bee. e 4ee. 8 see. 8 288 ~ 8 1.88. e e.e 8~8 iee. e Bee. e see. e 4ee. e Bee. 8 see.e TIME (SEC)

CASE S 0 HZP Both ARVa and Both MFRVa

Figure 5 NSSG NSSQ 8 BBE+86 v.eeE+es e.eeE+86 6 BBE+86 a

E lA 4 BBE+86 3.eeE+es E,BBE+86 1+BBE+86 e.e 188 ~ 8 288 ~ 8 388 ~ 8 4ee. e 6ee. e eee. e Tee. e TINE (SEC)

CASE 6 0 HZP Bath ARVa and Bath NFRVa

Figure 6 DKSTAR 8~ 8

-aee.e

-4es.e

-Bss ~ 8

-888 ~ 8 E

0 Q.

4l

-csee. e 0

8 5

L 0

-race.e

-x488.8

-1see. 8

-csee.e

-aces.e e.e see.e aee. e Qese 8 4ee. e see. e see.e 788 ~ 8 TIME (SEC)

CASE 6 0 H2P Both ARVe and 8oth MFRVe

s I Figure 7 DKRATE 48 '

3e. e 28 ~ 8 0

5 I

8 0 18 ~ 8 0.

I 0

0:

C 0

'et 5

8 8~ 8 0

C M

4l

~ Q 4l L'8 0

S

~ 8 0

I-

-28 ~ 8 38 ~ 8

-4e. e e.e 28 ~ 8 48 ~ 8 68 ~ 8 se. 8 188 ~ 8 xe. e 3e. e 68. e ve. e 98 ~ 8.

TINE (SEC)

CASE 6 0 HZP Both ARVa and Both NPRVs

Figure 8 QNCt R

e. eese e.ee4e 8~ 8838 C

0

~ Of 4l 0

0

%J s

3 0

Q.

0 X

e.eeae

e. 8818 1 ~ 46E-86 e.e lee. e'ee.e 3ee. e 4ee. 8 688 ~ 8 6ee. e 788 '

TINE (SEC>

SLB 8 ~ 66 lbs/hr Manual Actlcns

4 TAVQ Figure 9 668 ~ 8 64e. 8 s2e. e see. e 468 ~ 8 46e. 8 44e. e 42e. e e.e see. 8'88 ~ 8 388 ~ 8 4ee. 8 see. e see. 8 788 ~ 8 TIME <SEC)

SLB 8 66 1bsrhI. Nsnual Actions

Csalt al r ~

Figure 10 PR0P a4ee. 8 228 8 ~ 8 aeee.e 1see. e 1688 ~ 8 s

s fL I

14ee. 8 5

5 8

lL N

L CL 1288 ~ 8 1eee. e see. 8 see. 8 4ee. 8 e.e 188 ~ 8 aee. 8 388 ~ 8 488 ~ 8 see. 8 see. 8 788 ~ 8 TINE (SEC)

St-B 8 ~ 66 lbsyhr Manual Actions

PS F~ire 11

'xee'.8 1888 ~ 8 see. 8 see. e 788 ~ 8 see. 8 see. e 4ee. 8 388 ~ 8 288 ~ 8 8~ 8 see. e 2ee. e 388 ~ 8 488 ~ 8 688. 8 7ee. e TINE (SEC)

SLB Bo66 lbs/hr Manual Actions

VSSe Fiuure 12

3. ~ 48E+86 NSSP 1 '8E+86 1 ~ RBE+86 1.1eE+e6 0

s 1.eeE+e6 E

Cl Ol eeeee.e 6eeee. e 7eeee.e 6eeee.e B.e 188 ~ 8 EBB ~ 8 388 ~ 8 4ee. e 6ee.e 6ee.e 788i8 TINE (SEC)

SLS 8 ~ 66 lbs/hr Manual Actions

II I DKSTAR Figure 13 e.e

-aee.e

-4ee.e

-6ee.e

-See.e E

0 0.

4l

-1eee. e 0

a a

0:

0 I 1288 ~ 8

-14ee. e

-16ee. e

-1888 ~ 8

-aeee.e 8~ 8 1ee. e aee. e see. e 4ee. e see. e See. 8 see. e TIME (SEC)

SL8 8~ 66 iba/hr Manual Actions

h OKRATE Figure 14 ee.e 4e. e 0

rr ae. e 8

0 0.

r L'

0 rr B.e C

M 44 4J 0

rr L

0 -ae. 8 I-

-48. e

-se. e B.e se.e fee.e use.e aee.e as' 388 ' 368 '

TIME (SEC)

SLB 8 ~ 66 lbhr Nrnusl Actions