ML18044A522

From kanterella
Jump to navigation Jump to search
Forwards Completed SEP Topic XV-18, Radiological Consequences of Main Steam Line Failure Outside Containment. Assessment Compares Util Facility Design W/Criteria Used by NRC in Licensing New Facilities
ML18044A522
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-15-02, TASK-15-2, TASK-RR NUDOCS 8002150220
Download: ML18044A522 (8)
v • d • e


Text

.... -

~-,,

      • .i Docket No. 50-~55 Dockef NRC PDR Local PDR

'ORB Reading NRR Reading DEisenhit RVollmer OSLO OI.&E (3)

DLZi e111ann-

  • JWetmore*

Mr *. Davi* d P. Hoffman Uucl ear L1.cens fog Admi nfstrator

~Consumers* Power Company

~~~~th.* * * -

  • JAN.2-9 19~0*

212 Wesi Michigan Avenue -

Jack son; Michigan 4920l

Dear Mr. Hoffman:

TERA

. ACRS (l6)......

.otru.tchfi.el d. {2) *

.~~ -.

RE:

CQMPLETION OF 'SEP TOPIC xv.::-ia 'J~ad1olog1~al Conseq$u~mces ~f-r,1~i~ -Steam -

Line Fa1lure: Outsfde Containment.

  • ; /

. -: Your letter. dated December t. 1'979 iild1cated that* you h~ve ex~mi~~d our draft evaluation of_ the subject topic da'ted. Hovember a. 1979.. You suggf;lsted*

  • . editorial or corrective changes* to the assesS.m~nt to make 1t more -accurately reflect you.r facility design. We.have incQrporated.your suggested.modift-
  • c.ations -1n. tne enclosed assessment. With _these mod1ficat1on~s our.review*

_,_ *

  • of -SEP Topic xv... 1a is complete ~nd wiJ-1 be-a basic 1riput to t~e in_tegrated
  • ' * - as.sessment of your fac1 li_ty.

.. * :*._Th~. *~ubject. :a~sess~ent. c~a-res.. your.. !facil~ty- ~esign -with: "th~ *crite;~a.... *

-curr~ntly.used bYthe staff-1n 11censing na1-fa~Hit1es.* Th1*s.assessment

  • may need to'be re*exam1ned 'ff you modi.fy your. facility or. if -th_e criteria*-.

-.are changed before- ~e complete oµr integrated ass~ssment..

~

\\'.

,(.

-~,..

... -- ~'

l -~ :.

, ti * '

Enclosure:

Comp 1 eted SEP

. Topic x-v-1 e cc w/enclosure:

See next page S1.ncerelY.~.

*.'.b* *-,.

Signed Y~-

. 1 1na1

~:!ie 1.i-~~~~~

-~**-***~***

.. DenniS L* Ziemann,. Chief..

-*Operating ~eactors Branch #2 D1v1sfon of Operatin~1 Reactors.

. ~ - '

~

.l

  • ~~
  • . 'O.FFICE...

DOR: ORB.#2 D~~B #2.. P.Q~~--Q~-~.!.~.....-..... :....... _...... :...... :... :......... < ********

SURNAME ~-... __ j __ w_~_ t_._-~_o_* ~---~- ;_*~---~.--.. *_ *H. -~Vt_.-_._h ti.. *.*.*.**.*.*_*_*._*

_D_L.ZL~n:i9nrJ:.. :.:.................... :.. $_()_Q2~.0.~-~9.-.~-.

. DATE~.-:~ !ti:!.~?."*......

1/-'1!~?. _...... ~ !.1!.~?-.. :.......... *... _......,-.. ::..... -..... -. --. -. -......... :.,. : -.

NRC FORM *318 (9-76) NRCM 0240 i:ru.s. GOVERNMENT PRINTING OFFICE: 1979-289-369

~r. David P. Hoffman cc M. I. Miller, Esquire Ishar.i, Lincoln & Beale Suite 4200.

One First National Plaza Chicago, Illinois 60670 Mr. Paul A. Perry, Secretary Consuners Power Company 212 West Michigan Avenue

  • Jackso~, Michigan 49201 Judd L. Bacon, Esquire Consuners Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Myron M. Cherry, Esquire Suite 4501 One IBM Plaza Chicago, Illinois 60611 Ms. Mary P. Sinclair

. Great Lakes Energy Alliance 5711 Summerset Drive Midland, Michigan 48640 Kalamazoo Public Library 315 South Rose Street Kalamazoo, Michigan 49006

  • Township Supervisor Co.vert Township Route 1, Box 10 Van Buren County, Michigan 49043 Office of the Governor (2)

Roe~ l - Capitol Building Lansing, Michigan 48913 Director, Technical Assessment Division Office of Radiation Programs

(;.W-459)

U. S. Environmental Protection Agency Crystal Mall #2 Arlington, Virginia 20460 January 29, 1980 U. S. Environmental Protection Agency Federal Activities Branch Region V,Qffi ce ATTN:

EIS tOORDINATOR 230 South Dearborn Street Chicago, Illinois 60604 Charles Bechhoefer, Esq., Chainnan Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D. C.

20555 D~ George C. Anderson Depart~ent of Oceanography University of Washington Seattle, Washington 98195 Or. M. Stanley Li vi ngston 1005 Calle Largo Santa Fe, New Mexico 87501 Resident Inspector c/o U. S. NRC.

P. O. Box 87 South Haven, Michigan Palisades Plant ATTN:

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

49090 ATTN:

Richard E. Schaffstall

Suite l 050 Washington,.D. C.

20006

~...

e Complete - January 2, 1980 Palisades Topic IV-18 ladiolog1ca1 Consequences of Ma1n Steam Ltne Failure Ouu;de tontairwnent The safety objective of this topic is to assure that the releases from this postulated event w111 not result il'I exposures 1n excess of the established guidelines.

The rupture of a 11ain steam line is considered a limiting fault not expected to take place during the lifetime of the plant.

~evertheless, tt is postulated because its consequences could include the release of significant amounts of radioactive material. In particular, the failure of a steam line outside contairvnent would result tn the release of activity contained within the secondary system, in addition to opening a potential. albeit small path for the release of reactor coolant to the envirorwnent via postulated steam 1ener1tor 1ealc.s.

An analysis of the radiological consequences of e matn steam 1tne f~11ure at the Palisades plant has been performed following the assumptions and procedures indicated in the Appendix to S.R.P *. 15.1,5, "Radiological Consequences of Main, Steam Line Failures Outside "Containment (PWR), 11 The specific assumptions made regarding the plant conditions prior to the postulated accident and the ~xpected responses are listed in Table XV-1.

In particular, it has been assumed that one steam generator is blown dry within 60 seconds following the accident, and that 1 gpm of reactor

' ~. '

- 2..

coolant is released directly to the environment during the ftrst two hours. This 1s 1n accordance w1th Techntcal Spec1f1cat1on 3,1,5 which limits the allowable steam generator primary to secondary leakage to 0.6 gpm in any one steam generator.

In addition, it has been assumed that prior to the accident t~e primary and secondary coolant activities were at the maximum levels allowed by the Technical Specifications 3.1.4 and 3. 1.5. An evaluation of this accident in support of Amendment 31 to the provisional operattng license in November 1977 concluded that no additional fuel clad fatlures would occur.

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. 15.1.5.

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

This completes the evaluation of this SEP topic. Since the plant design conforms to current licensing criteria, no additional SEP review is required.

Topic XV-18 (Palisades)

References

1. Palisades Plant - FSAR.

Secttcn 14,14

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

June 26, 1978 "Palisades Plant - Steam Generator Operating H1story Questionnatre,"

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 Provisional Operating L1cense No.

DPR~20. Palisades Plant. Section 4.4 Docket 50-255.

5. Palisades Plant Technical Specifications
e.

TABLE XV-1 Assumptions Made in Analysis of the Rad1ologic~l Consequences of Postulated Tube Failure,.. Main Steam Line Failure and Control Rod Ejection Accidents

1. Reactor power= 2650 ~th.
2.
3.
4.
5.

Loss of offsite power following the accident.

Primary coolant activity.Q_rior to the accident of 1.~Ci/g of Dose Equivalent I-131 and 100/f ~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.

6.

Secondar~ coolant activity prior to the accident of O.l ~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 rel~ase at exclusion area boundary boundary = 3. 4 x 10-sec/m For the Steam Generator Tube Failure Accident
1.

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 h*lf 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.

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

0.3% of rods suffer clad damage.

3. o.1 % 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

l. 7

< 0.01 Accident Steam Line Failure 2.6

< 0.01 Accident with Previous Iodine Spike*

Rod Ejection Accident**

Case 1 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.

Retrieved from "https://kanterella.com/w/index.php?title=ML18044A522&oldid=5025805"