ML18143A837

Notice of Shutdown of Plant in October 1972

ML18143A837
Person / Time
Site:	Ginna
Issue date:	09/29/1972
From:	Amish K Rochester Gas & Electric Corp
To:	Skovholt D US Atomic Energy Commission (AEC)
References
Download: ML18143A837 (10)

Text

AEC DXSZRXBUTXON FOR PART 0 DOCKET YIATERXAL'EMPORARY FORYA I ~

FROM:

.'Roch'ester Gas 8 Electric Corp.

Rochester~

N. Y.

14604 Keith W. Amish To ~

Mr. Skovholt CLASS:

U PROP INFO DATE OF DOC:

9-29-72 ORIG INPUT DATE REC'D LTR 10-6-72 CC No CYS REC'D FX MEMO SENT AEC PDRiX SENT LOCAL PDR I DOCMT No'ESQRXPTXON:

.Ltr fund. shing info regarding October 1972 Shutdown~

& trans the following:

. 50-N, ENCLOSURES:

Outline of Some core characteristics for Cgcle.3e

~ ~ ~ ~ ~ ~

PLANT KVSS:

R. E. Ginna DO NOT REMOVE hIlIIlIIItLBhFj FOR ACTION XNFORMATXON 10 2 AB BUTax(L)

$7/

Copies CLARK(X,)

W/

Copies GOLLER W/= Copies KNXEL(L)

W/

Copies SCHWZNCZR(X,)

W/

Copies STOLZ(I,)

W/

Copies VASSALID(X,)

W/

Copies H.

DENTON'/

Copies SCHEMEL(L)

W/

Copies

~ ZIEMANN(L)

W/9 Copies CHITWOOD(FM)

W/

Copies DIcKzR(zmVIRo)

W/

Copies mrxGHTom(zvrzao)

W/

Copies YOUNGBLDOD(ENVIRO)

'W/

Copies W/

Copies FX TECH REVIEW

~ -OGC~--.ROOM -P~506A-SCHROEDER

~ YiiTZING/STAFF

~MACCARY CASE FLANGE GIAMBUSSO

&PA>7LICKI

~ BOYD-L(B~7R)

~SHAO DEYOUNG-L(PWR)

~KNUTH M SKOVHOLT-L

~ STELA P.

COLLINS WYOORE W HOUSTON REG OPR

~TEDESCO RIIE lh REGIOE (2) mIOEG I

YiORRIS W LAXNAS STELLE

~ HWAROYA

~VOLIÃER DENTON

GRIMES, GAMMXLL KASTNER BAXZQK FINE EEVIBO MUIIGII DICKER KNIGHTON YOUNGBIDOD PROJECT LEADER HARLEM' F

8c M SMXQ~Y NUSSBAUMER LIC ASST.

SERVICE L

MASON L

WILSON L

KARI L

.SMITH L

GEARIN L

~ DIGGS L

TEZTS L

'LEE L

WADE SHAFER F

&, M BRO>7N E

G. >7ILLIAYS E

E.

GOULBOURNE L

PLANS YiCDONALD DUBE INFO C,

MXLZS W l>>rDCAL PDR or

~ 1-DTXZ(mmmlLTHY) 1 NSIC(BUCHANAN) 1-ASLB-YORE/SAYRE WOODWARD/H. ST, g

16-CES ACES ESMIEEE 8 Ill EXTERNAT DISTRIBUTION (l)(5)(9)-NATIONALLAB'S 1-R.

CARROLL-Oc) GT-B227 1-R. CATLIN~,A-170-GT 1-CONSULAMT'S S~

TO &C ASST NEWMAN(/BLUME/AGABIAN R, DIGGS FOR DXST Om 10-10-72 1-PDR-SAN/LA/NY l>>GiRK3 LELIDUCHE BROOKHAVEN NAT. LAB 1-AGMED(WALTER KOESTER, Rm C-427p GT),

1-RD. ~. MULXZB.~.F-309GT

I

~

~

1 '

~ 0

~

~

A

I ZEg izzziEIE iiiiiiiiII

'ROCHESTER GAS AND ELECTRIC CORPORATION o 89,EAST AVENUE, ROCHESTER, N.Y. 14604 KEITHW. AMISH SCNIOR VICC PRKSIDKNT KCKCTRIC AND STCAM TCCCPHONK ARCA CODC TIS 546.2700 September 29, 1972 Mr. Donald J. Skovholt Assistant Director for Operating Reactors Directorate of Licensing U.S. Atomic Energy Commission 7920 Norfolk Avenue

Bethesda, Maryland 20014

Subject:

R.E.

Ginna Nuclear Power Plant Unit No.

1 October 1972 Shutdown - Docket 850-244

Dear Mr. Skovholt:

The Ginna nuclear plant will be removed from service in October of this year to replace the forty-eight remaining first core fuel assemblies.

These assemblies were initially unpressurized and many of the assemblies were observed during the Spring 1972 refueling to have had collapsed sections of the cladding.

The forty-eight replacement assemblies are pre-pressurized with Pelium and have fuel pellets of 94% theoretical density.

Following this replacement, all fuel in the reactor will be pre-pressurized.

Rochester Gas and Electric Corporation recognizes that the U.S, Atomic Energy Commission has not completed its evaluation of fuel densification phenomena.

Accordingly, Rochester Gas and Electric proposes to continue, on an interim basis, to limit the..Ginna power level to 1266 thermal mega-

watts, as authorized in your June 23,,1972 letter.

Rochester Gas and Electric will also restrict the operation of the Ginna Station to comply with the conditions defined in our June 12, 1972, correspondence to you as supple-mented by Attachment A of your letter of June 23, 1972.

No modifications to the Technical Specification's are required as a result of this refueling.

With this new core configuration and under this proposed mode of operation, all safety margins will be essentially the same or greater than during the past operating cycle.

We anticipate that the plant will be returned to service on November 11, 1972, for a cycle length of approximately 15 months.

Within 60 days after our return to power, we intend to submit analyses supporting operation at the licensed rating of 1520 MWt.

An outline of some of the core nuclear characteristics for Cycle 3

is presented in an attachment to this letter, showing a comparison with the values for the Cycle 2 loading.

Attachments Very truly yours, Keith W. Amish

r~

a

'~lt

~

~ 4

ATTACHMENT A The forty-eight assemblies to be loaded at the coming refueling comply with 5.3.1 Reactor Core of the Technical Specifications.

Two en-richments will be employed with thirty-six assemblies at 3.30 weight per-cent U-235 and twelve at 2.25 weight percent.

The higher enrichment assemblies will be loaded on the periphery while the twelve lower enrichment assemblies will be interspersed with partially burned fuel in the interior.

These forty-eight fresh assemblies are identical in mechanical design with the sixty-one assemblies loaded in April, 1972.

A summary of the core physics characteristics is presented in Table 1.

r. t f

11

TABLE 1

SUMMARY

OF CORE PHYSICS CHARACTERISTICS Expected boron concentration (ppm) for the following situations:

HZP, BOL, no Xe, Peak Sm, ARO HZP, BOL, no Xe, Peak Sm, D rods in

HFP, no Xe, Peak Sm, ARO HFP, equilibrium Xe, 9 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, ARO HZP-BOL control rod worths

(-%p)

Control bank D

All rods in HFP-1 00 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> control rod worths Contr ol bank D

Al1 rods in HZP-EOL control rod worths All rods in HZP-BOL moderator temperature coefficient, all rods out, pcm/'F KFP-BOL moderator temperature coefficient, all rods out, pcm/'F HFP-EOL moderator temper ature coefficient, all rods out, pcm/'F

~Cele 2

's-Loaded

'1280 1177 1092 816 0.96 7. 21 0.97 7.52 3 ~ 3

-9.9

-32.0

~Cele 3

1602 1482 1425 1140 1.03 7.,1 8 1.05 7.10

+ 2*

-5.4

'-34.8 A similar value was measured for'the initial core

I

e i e

Cycle 2

~Cele 3

HFP-BOL inverse boron worth, ppm/XP HZP-BOL inverse boron worth, ppm/X<

Cycle reactivity lifetime (MlJD/NTU)

Effective full power days (9 1520 MMT)

Maximum Fuel Rod Relative

Power, FR (no engineering or uncertainty factors)

HZP-BOL, all rods out HFP-100 hours, all 'rods out HFP-100 hours, bank D inserted HFP-EOL, all rods out HFP-EOL, bank D inserted Nuclear axial peaking factor, FNZ HFP-100 hours, All rods out

-ill

-106 8300 259 1.55 1.47 1.65 1.38 1.31

-126

-116 15150 475 1.51 1.48 1.66 1.30 1.44 1.31

~

~

~