ML20040F609

RO:30-day Rept & 10-day Rept Per App B ETS Re Excessive Liquid Waste Discharge & Excessive Level of Radioactivity.Caused by Steam Generator Primary Side to Secondary Side Leakage.Doses within Bases for 2.5 Ci Limit

ML20040F609
Person / Time
Site:	Millstone
Issue date:	01/29/1982
From:	Mroczka E NORTHEAST NUCLEAR ENERGY CO.
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
MP-2-5041, NUDOCS 8202090404
Download: ML20040F609 (4)

Text

- - -- _ -- - -- - - - ---- - - - - - - - - - - - - - - - - - - - - - -

.; a nostrunarr irrn.rnus L L lJ 55555i5E

'::r's?.,'Jrr'l'*Tf" ES[ sis """""""

January 29, 1982 MP-2-5041 Mr. Ronald C. Haynes ~-

Regional Administrator, Region 1 i

~\

~

Office of Inspection and Enforcement U.S. Nuclear Regulatory Comission ,

631 Park Avenue j King of Prussia, Pennsylvania 19406 ,

j in ,C

Reference:

Facility Operating License DPR-65 n  !~"

%?,D Docket No. 50-336  %

V,'y Cf -

[/g

'/

Dear Mr. Haynes:

'N This letter forwards the 30 day report required to be submitted pursuant to Millstone Unit 2 Appendix B Environmental Technical Specifications, Section 5.6.2.a.(2) and the 10 day report required pursuant to Millstone Unit 2 Appendix B Environmental Technical Specifications, Section 5.6.2.b.(1). The report concerns liquid waste discharge exceeding 2.5 C1/ reactor / calendar quarter per Specification 2.4.1.2.c and a confirmed measured level of radioactivity in an environmental medium exceeding ten times the control station values.

Yours truly, NORTHEAST NUCLEAR ENERGY C0! PANY

/&f c

. J. Mroc sa Station Superintendent Millstone Nuclear Power Station EJM/SLS:mo

Attachment:

cc: Director, Office of Inspection and Enforcement, Washington, D.C. (20)

Director, Office of Management Information and Program Control, Washington, D.C. (2)

Director, Division of Reactor Licensing 8202090404 820129 PDR ADOCK 05000336 O

PDR

' 6(,ds/

_ - - - - - - - - n/B J,

• O Page 2 1 ATTACHMENT ,

Event Description 1981 Fourth quarter liquid radwaste discharges were 3.14 curies. Environmental Technical Specification (ETS) 2.4.1.2.B require that "the equipment installed in the liquid waste system shall be maintained and shall be operated to process radioactive liquid wastes prior to their discharge when the projected cumulative release could exceed 1.25 Ci/ reactor / calendar / quarter, excluding tritium and dissolved gases". .During the time period starting on September 6,1981, until the end of the calendar quarter this requirement was met. Also ETS 2.4.1.2.c. states "if the cumulative release of radioactive materials in liquid effluents excluding tritium and dissolved gases, exceeds 2.5 Ci/ reactor / calendar / quarter, the licensee shall make an investigation to identify the cause of such releases, define and initiate a program of action to reduce such releases to design objective levels and report these actions to the Conmission within 30 days from the end of the quarter during which the release occurred". Submittal of this report satisfies this requirement.

Cause and Corrective Action The cause of the increased liquid radwaste discharge was determined to be steam generator primary side to secondary side leakage. This was confirmed by a Steam det Air Ejector radiation alarm on September 6,1981. Due to the temperature of the steam generator blowdown it can not be processed through the liquid radwaste system. During this time period the radioactive discharges were monitored in accordance with technical specification requirements. After the reactor trip on October 15, 1981 until December 5,1981 shutdown for refueling, the radioactivity of the blowdown was monitored on a daily basis to ensure that technical specification limits would not be exceeded.

Af ter plant shutdown for refueling a pressure test on the steam generator's secondary side revealed that one (1) previously plugged tube in each steam generator was leaking. Further investigation is being performed to determine the condition of the steam generator tubes.

Effect of Increased Discharge Levels Offsite doses from Millstone Unit 2 liquid effluent were calculated and are tabulated on Attachment I. The calculated offsite doses, while greater than typical quarterly liquid doses from Unit 2, are well within all applicable limits and 10CFR50, Appendix I, design guidelines and hence result in no measurable effects on health or safety of the general public. In actuality, the doses are well within the bases for the 2.5 Curie limit which is more applicable to sites with drinking water pathways.

In addition to calculation of offsite doses, special environmental samples were collected to further evaluate the elevated liquid releases. These samples include oysters and flora sampled in and near the quarry. The only effects noted above normal sample results were elevated levels of I-131 in flora within 500 feet of the quarry. This was expected due to the higher than normal release of this isotope during the fourth quarter. The elevated levels in the flora sampled (seaweed) resulted in no dose to the general public since seaweed is not normally consumed.

j

Page 3 ATTACHMENT The flora samples (seaweed) were collected because they are good indicators of short lived isotopes. The samples collected on December 7,1981 from within 500 feet of the discharge indicated a value of 2.3 10.2 pCi/g (wet) of I-131.

This value is ten times above routine control station values and therefore is an anomalous measurement per ETS 5.6.2.b.(1). Due to a misunderstanding the report for the anomalous measurement was not completed within the required ten day interval after confirmation. Therefore this report also fulfills that ten day report requirement.

, , .o.

ATTACHMENT 1 Millstone 2 Liquid Doses For The Fourth Quarter 1981 Units Oct. - Dec. 1981 Maximum Individual Dose

a. Whole Body (teen) mrem 1.1 E-2

.b. Maximum Organ (teen thyroid) mrem 5.5 E-2 Population Dose (0-50 miles)

. a. Whole Body person-rem 3.5 E-2

.. b. Maximum Organ j (thyroid) person-rem 1.8 E-1

, Average Dose (0-50 miles)

a. 'Whole Body mrem 1.1 E-5

b. Maximum Organ (thyroid) mrem 5.4 E-5 O

se e.

p, .

• 2

- - > + , . - ,