ML18044A521

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Forwards Completed Assessment of SEP Topic XV-12, Spectrum of Rod Ejection Accidents (PWR) - Radiological Consequences. Suggested Mods Have Been Incorporated
ML18044A521
Person / Time
Site: Palisades Entergy icon.png
Issue date: 01/29/1980
From: Ziemann D
Office of Nuclear Reactor Regulation
To: Hoffman D
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
References
TASK-15-12, TASK-RR NUDOCS 8002150202
Download: ML18044A521 (8)
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Text

...

Docket No. 50-.255

. Mr. David p*. Hoffman Nuclear Licensing Administrator*

Consumers Power Company 2l2 West Michigan Avenue *

  • 'Jackson, M1chfgan.. -4920l

-,. Dear Mr. Hoffmam'.

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Docket NRC PDR.

Local PDR.

ORB Reading NRR _Reading *

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  • C-OMPLETION :oF: SEP: ropi~. xv-12.* Spect~um.* of** Rod. EJ~ction'*Acc.ident:s < PHR)*:

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I Rad1olog1ca1. Consequences. " * *.

  • Your letter.date.d December 7, 1979 indicated that you have.examined our draft*.

evaluation of the. subject topic *dated November 24, 1979.i You *suggested "...

editorial o*r cory;ectiye cha.nges to the assessment to make it more accur~tely *

>reflect your fac11 fty des*ign;'.

We have tncorporat-ed.your suggested modifi-* *

  • c;at.1ons ln the.*ericl o*sed assessment. :: With ~hese modi ficat1ons* ou.r r~v1 e\\.t o.f.....

the Rad1olog1cal Consequnces Portion of ~SEP Topic XV-12-. is complete and"

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will l)e.~ *bas:fc. in.put.to *the integrated assessment of-your. fac.i11ty.

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-~.:currently used by the* staff 1.n licensing: new. f~c1lit1es *. This assessment._**..

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  • may need'to b~ *re;.examh1ei:t if YQU modify your facility or~*rf. the criteria.* _.-.*

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Enclosure:

. ~omp.1 eted SEP. *

- TopiC XV-12

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Dennis :L: *. Ziem.ann :

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  • . ~.nef1nis* L. Z1emann, _Chief*...
  • *:..'-Operatf.ng Reactors Branch #? *
    • DivisJon of Ope.rating Reactors

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-tl'u:s. GOVERNMENT PRINTING OFFICE: 1.979-289-369

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rf Mr. David P. Hoffman cc M. I. 'Miller, Esquire Isham, Lincoln & Beale Suite 4200 One First National Plaza Chicago, Illinois 60670 Mr. Paul A. Perry, Secretary Consumers Power Company 212 West Michigan Avenue Jackso~, Michigan 49201 Judd L. Bacon, Esquire Cons:.m:ers Power Company 212 West Michigan Avenue Jackson, M~chi;:~ 49201 Myron M. Cherry, Esquire Suite 4501 One IBM Plaza Chicago, Illinois 60611 Ms. Mary P. Sinclair Great Lakes Energy Alliance 5 71 l Summers et D ri ve Midland, Michigan 48640 Kalamazoo Public Library 315 South Rose Street Kalamazoo, Michigan 49006 Township Supervisor Covert Township Route l, Box l 0 Van Buren County, Michigan 49043 Office of the Governor (2)

Room l - Capitol Building Lansing, Michigan 48913 Director, Technical Assessment Division Office of Radiation Programs (AW-459)

U. S. Environmental Protection Agency Crystal Ma 11 #2 Arlington, Virginia 20460 January 29, 1980 U. S. Environmental Protection Agency Federal Activities Branch Region V Office ATIN:

.EIS COORDINATOR 230 South Dearborn Street Chicago, Illinois 60604 Charles. Bechhoefer, Esq., Chairman Atomic Safety and Licensing Board Panel U. S. Nuclear Regulatory Cormiission Washin~ton, D. C. *20555 Dr. George C. Anderson Department of Oceanography University of Washington Seattle, Washington 98195 Dr. M. St...anl ey Li vi ngston 1005 CalTe Largo Santa Fe, New Mexico 87501 Resident Inspector c/o U. S. NRC P. O. Box 87 South Haven~- Michigan 49090 Palisades Plant ATIN:

Mr. J. G. Lewis Plant Manager Covert, Michigan 49043 KM C, Inc.

ATTN:

Richard E. Schaffstall 1747 Pennsylvania Avenue, N. W.

Suite 1050 Washington, D. C.

20006

Complete -~uary 2, 1980 Palisades Topic XV-12 Spectrum of Rod Ejection Accidents (PWR).. Radiological Consequences The safety objective of this review is to assure that the releases from this postulated event will not result in exposures 1n excess of the established guidelines.

An analysis of the radiological consequences of a postulated control rod ejection accident has been performed following the assumptions and procedures indicated in Regulatory Guide 1,77 and the Appendix to S.R.P. 15.4.8, "Radiological Consequences of Control Rod Eject1on Accident. (PWR)." The specific assumptions made regarding the plant conditions prior to the postulated accident and the expected responses are listed in Table XV-1.

In particular, it has been conservatively assumed that the occident is followed by a complete loss of offs1te power. Therefore, the plant 1s cooled down by releasing secondary steam to the environment through the safety and relief valves.

In addition, it has been assumed that 0,3%

of the rods suffer clad damage and 0.1% of the rods have at least incipient centerline melting as a result of the accident. This 1s 1n accordance with the assumptions in Section 14.16 of the FSAR.

The estimated site boundary doses resulting from this postulated accident (see Table XV-2) have been found to be within the 10 CFR Part 100

. guidelines as specified in the Acceptance Criteria for S.R.P. 15,4.8 The estimated doses at the low population zone (LPZ) are lower.

  • On the basis of these results, we conclude that the Palisades plant design is acceptable with respect to the radiological consequences of a possible control rod ejection accident, and that the risk presented by this postulated accident is similar to that of plants licensed under current criteria.

Topic XV-12 (Palisades)

References

1.

Palisades Plant - FSAR.

Section 14,16

2. Letter from D. P. Hoffman, Consumers Power Company, to the Director, NRR.

June 26, 1978 "Palisades Plant ~

Steam Generator Operating History Quest1onna1re,M Docket 50-255

3.

Consumers Power Company - Steam Generator Repair Report for the Palisades Plant. Docket 50-255 January 1979,

4. Safety Evaluation by the Office of Nuclear Reactor Regulation Supporting Amendment No, 31 to Prov1s1ona1 Operating License No. DPR-20.

Palisades Plant Docket No. 50-255 November 1, 1977.

TABLE XV-1 Assumptions Made in Analysis of the Radiological Consequences of Postulated Tube Failure,

~ain Steam Line Failure and Control Rod Ejection Accidents

1. Reactor power= 2650 Mwth.
2.
3.
4.
5.
6.

Loss of offsite power following the accident.

Primary coolant activity Q_rior to the accident of l.~Ci/g of Dose Equivalent I-131 and 100/r ~Ci/g of noble gases.

Iodine spiking factor of 500 after the accident.

Primary coolant activity of 40.~Ci/g of Dose Equivalent I-131 at time of accident for cases assuming a previous iodine spike.

Secondary coolant activity prior to the accident of 0.1 ~Ci/g Dose Equivalent I-131.

7.

Iodine decontamination factor of 10 between water and steam.

8. 0-2 hour X/Q for gro~nd re13ase at exclusion area boundary boundary = 3.4 x 10-sec/m For the Steam Generator Tube Failure Accident
l. Failed steam generator is not isolated during the first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> following the accident.
2.

98,000 lb. of primary coolant leak to the secondary side of the failed steam generator through the failed tube during the first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (one hJlf during the first 30 minutes),

3.

All releases through the secondary side safety and relief valves.

4.

No additional fuel clad failures as a result of the accident.

For the Main Steam Line Failure Accident

1. Total primary to secondary leak rate of 1. gpm.
2.

No additional fuel clad failures as a result of the accident.

For the Control Rod Ejection Accident

1. Total primary to secondary leak rate of 1. gpm.

Z.

0.3: of rods suffer clad damage.

3. o.l % of rods have at least incipient center line melting.

TABLE XV-2 ACCIDENT DOSES AT NEAREST SITE BOUNDARY 2-hour Dose 2-hour Whole to the Thyroid (rem)

Body Dose (rem}

Tube Failure Accident

12.

0,4 Tube Failure Accident 60, 0,4 with Previous Iod1ne Spike*

Steam Line Failure

1. 7

< 0.01 Accident Steam Line Failure 2.6

< 0.01 Accident with Previous Iodine Spike*

Rod Ejection Accident**

Case l 3.6 0.05.

Case 2 1.0

< 0.01

  • For this accident sequence it is assumed that an iodine spike was initiated some time before the accident resulting in the highest coolant activity allowed by the Technical Specifications.
    • Case 1 assumes all releases through the secondary side safety
  • and relief valves. Case 2 assumes all releases through the containment.
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