ML18142B884

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LER 1975-006-00 for R. E. Ginna, Unplanned Insertion of Greater than 0.5% K/K with Reactor Subcritical
ML18142B884
Person / Time
Site: Ginna Constellation icon.png
Issue date: 03/25/1975
From: White L
Rochester Gas & Electric Corp
To: O'Reilly J
NRC/IE, NRC Region 1
References
LER 1975-006-00
Download: ML18142B884 (7)


Text

NRC DISTRIBUTION FOR PART 50 DQCI<ET MATERIAL (TEIt/IPORARY FORM)

CONTROL NQ:~~~MM FILE. INCID"-!.'T !'."-PC."..T FI F RQM: Roches ter Gas & Elec. Co ~ DATE OF DOC DATE REC'D LTR TWX RPT OTHER Rochester, N. Y. 3-25-75 4-3-75 XX I

.ORIG CC OTHER SENT AEC PDR XXX TO:

James P. O'Reilly i Signed SENT LOCAL PDR XXXX CLASS UNC LASS PROPINFO INPUT NO CYS REC'D DOCKET NO:

XXX '50-244

. DESCRIPTION: ENCLOSURES:

Ltr. trans the following.. ~ Abnorm Occurr. 8 75-06; on 3-12-75 con-cerning, boron concentration reduced in-advertently from 2068 ppm to 1975ppm.. ~

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W/ Copies .W < opies W/ Copies W/ Copies INTERNAL DISTRIBUTION REG F IL TECH REVIEW DFNTOiN LIC ASST INO .

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htKtt ROCHESTER GAS AND ELECTRIC CORPORATION D 89 EAST AVENUE, ROCHESTER, N.Y, 14649 LEON D. WHITE, JR. T E L E P ht O N E VICE PRESIDENT QCCI(Llil IJRII~<

ARE* CODE 71K 546-2700 1

I March 25, 1975 I Ohthtllc *'h~hI Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406

Subject:

Abnormal Occurrence 75-06, Unplanned insertion of greater than 0.5%+k/k with the reactor subcritical.

R. E. Qinna Nuclear Power Plant, Unit No. 1 Docket No. 50-244

Dear Mr. O'Reilly:

In accordance with Technical Specifications, Article 6. 6.2a, the attached report of Abnormal Occurrence 75-06 is hereby submitted. Two additional copies of this letter and the attachment are enclosed.

Very truly yours, L. D. White, Jr.

Attachment cc: Mr. Donald P. Knuth (40)

I~

g~

CONTROL BLOCK:

~ LICENSEE EVENT REPOR'I (PLEASE PRINT ALL REQUIRED IIIIFORMATIOIII)

LICENSEE UCENSE EVENT NAME LICENSE NUMBER TYPE TYPE gg N Y R E G 1 0 0 0 0 0 0 0 0 0 4 1 1 1 1',~01 7 89 14 15 26 30 31 32 REPORT REPORT

~ 7 8 CATEGORY I

57 D I 58 TYPE T

59

~

SOURCE 60 61 0 5 DOCKET NUMBER o 0 2 4 4 68 69 0 3 EVENT DATE 1 2 7 5 74 75 0 3 REPORT DATE 2 5 7 5 80 I

EVENT DESCRIPTION

[oO~] Durin ste s to rovide additional purification of reactor coolant, with the reactor at 7 8 9 80 cold shutdown, fboron concentration was reduced inadvertently from 2068 ppm to 1975 7 89 '0 Innsj ppm,) an insertion of more than 0.5% reactivity. Boron concentration was restored to 7 8 9 80 Qpg above 2000 ppm in preparation for refueling. (Abnormal Occurrence 50-244/75-06) 7 8 9 80 IOOI 7 8 9 PIEME 80 SYSTEM CAUSE COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPLER MANUFACTURER VIDLA11DN

[P]~CG 8 9 D D E MI N X ~N W 1 2 0 N 7 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION toOs] The procedure to valve in a converted deborating to cation demineralizer was'n 7 8 9 80

[opg] error; a deborating demineralizer was valved in instead. Measures to prevent 7 8 9 80

~10 recurrence are given on the attached page.

7 89 FACIUTY METHOD OF 80 STATUS IE POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION Q~g G ~oo o N/A b Anal sis of reactor coolant sam le 7 8 9 10 . 12 13 44 45 46 80 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE H H N/A N/A 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION P~7s ~OO O B N A 7 89 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION

~oo o N/A 7 8 9 11 12 80 OFFSITE CONSEQUENCES

@~5 N/A 7 t89 80 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION Qig 2 N/A 7 89 10 80 PUBLICITY N/A 7 89 80 ADDITIONAL FACTORS Jig In 1972 cation resins were placed in one of two Deborating Demineralizers after 89 80 Qqg cation demineralizer failure.

7 s 89 80 NAME: Bruce A. Snow PHDNE. 716-546-2700, Ext. 291-214 GPO 882 ~ 88T

0 l Licensee Event Report 2.

50-244/75-06 Measures to Prevent Recurrence

a. Correct the deficient procedure, S-3.3D, Cation Dem'ineralizer Operation.

The corrected procedure was reviewed in a Plant Operations Review Committee Meeting f35-75 on March 14, 1975.

b. Provide positive identification of the cation demineralizer at the location of the valve hand wheels. A sign for this location will be completed before May 1, 1975.
c. Review other procedures associated with the cation demineralizer to verify adequacy. This was completed on March 18, 1975 by the Operations Engineer.

1 A/ ~ v

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