ML19220B686
| ML19220B686 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/28/1969 |
| From: | Boyd R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Racquel Powell US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 7904270216 | |
| Download: ML19220B686 (6) | |
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' 23, 1969 January Reger S. Boyd, Assis tant Director for Reacter Projects, ORL THRU:
Rober: L. Tedesco, Chief, Reac tor Proj ect 3 ranch 2, ORL m
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, L, C v. _...,].. t, _ ; _ ns A =eeting was held with representatives cf Jersey Central Power i Light Cc=pany (JC?L) en January 15, 1969 in 3ethesda.
The principal purpose of the =eeting was to consider Jersey Central's preposed acticn regarding A=end:ent No. 6 whi:h will discuss the change to relocate the Cyster Creek Uni: No. 2 to the Three Mile Island site in Pennsylvania.
At this =eeting, Sabcock and Wilcox also presented 1:s analysis of eff ects of radiolytic hydrogen follcwing the LOCA, and the ef fects of nitregen blevdown on the core heatup anal sis.
f Attach =en: A lists the =eeting attecdance.
1.
?SAR f or Three Mile Island Unit,N,o.
2 Jersey Central Power & Light Cc=pany will sub=1: A=end:en: No. 6 on February 17, 1969 which will officially change the site location c:
the proposed 2452 Mwt pressurized water nuclear generating facility frc= the o' 'ginal Oyster Creek site in New Jersey to the Three Mile Island site in Pennsylvania.
In order to expedite the DRL review, A=end:ent No. 6 will cover all previous changes in the facility design and PSAR ite=s affected by the proposed site relocation.
A=end ent No. 6* will ec=pletely replace the presen: Oyster Creek Unit 2 PSAR Volu=es 1 through.
The following changes were discussed with JCPL and are considered as areas affec:ed by the change of site:
Or:anization Owner.
Jersey Central Operator Metropolitan Idison
- Inf or:atien presented in the Three Mile Island Uni: No. 2 PSAR which is not affec.:ed by the site change will be taken frc= the Cyster Creek Uni:
No. 2 PSAR and will include A=end=ents Nos. 1 through 5.
Infor:ation
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which is taken directly frc= the Ihree Mile Islanc. Unit No. 1 PSAR will be designated by a 6**, while those changes whic:t are recuired due to the site change will be designated by a 6 in the nargin. All pages of the Three Mile Island Unit 2 ?SAR which are changes frc= the Oyster Creek Unit 2 PSAR will be designa:ed by :he revision date of February 17, 1969 at the botte= of the page.
[31' ) [3" 7904270R0;3
Reger S. Scyd Organization (cen:inued)
Technical Assistance to Units 1 L 2.
General Public Utilities ASE (excluding ccoling cwers and switch-yard)
Burns & Rce Cons tructica Manager
. United Engineers & Construe:crs A&E for cooling towers, switchyard and consultant to 3&R for aircraft protection require: cats
. Gilbert Associates Nuclear Steam Supply Sabcock L Wilcox C;uality Assurance consultants
. MPR Associa:es Design Consultants
. Pickard 5 Lowe Associates Foundation Changes in the Unit 2 building design will be required since at the Three Mile Island site all foundations will be en bedrock.
External Power & Transfer =ers Gilbert Associates will be the ASE for the switch-yard. Two addi-tional transmission lines will be brcught to the Three Mile Island site frc= the south to increase offsite capabili:y.
Accident Analvsis Accident analysis which results in radioactivity releases will be revised using the Three Mile Island meteorology.
Cooling Tcwers Gilbert Associates will be the ASE for the Uni: 2 ccoling tcwers.
Was:e Discosal Burns and Roe will revise this section changing only the areas affected by the site change. Each plant will have its own waste handling syste:
except the Uni: 1 low-level liquid waste evaporator will be shared by e....
Fuel 5:crage Units 1 and 2 will share the dry fuel storage facili:y.81-154 4
Roger S. Scyd A.4. -. a.c.
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- rash design requirenents for nissile and fire prote::icn.
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Grouted Tendon Tests The report covering the latest grouted tenden :ests performed by 3 urns and Roe will not be included in the PSAR.
This grou:ed tenden report will be used as a ref erence reper to supper: design criteria.
Copies of this reper: will be provided inf ormally to us.
Shared Facilities JCFL will indicate in Unit 2 ?SAR all systens which will be shared with Unit 1.
Differences in Units 1 and 2 JCPL will include in the Unit 2 PSAR a section listing the differences between systers used in Units 1 and 2.
Emer2ency Planning Three Mile Island Uni: 1 energency plans will be revised to include Lw...<.,
2.
Quality Assurance and Centrol JCPL reviewed its proposed Quality Assurance and Control progran indicating hcw the progra= and organi:ation are affected by the si:e change. MPR is presently rewriting the Cuality Assurance section of the PSAR.
1: has been given unofficially a draf of the January 1, 1969 Nuclear ?:ver Plan: C_uality Assurance Criteria to crovide guidance as to current ORL concerns in this area.
3.
Nitrozen 31cwdcwn 3iw presented the results of its analysis of the nitrogen bicwdown
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from the core flooding tanks for a rupture of the hot-leg piping.
The results :o date indicate tha: the nitrogen expansion, fc11cving a het-le; pipe rupture, will cease with nitregen passing through :he core for a 1 or 22secend tire period. The analysis indicates that g
Roger S. 3cyd the a: cunt of nitregen which aculd pass thrcugh the core wculd not result in excessive fuel pin clad temperatures.
The =cdel used by 3&., alicws f or, nitrogen bypass cf the core via the outlet plenur thrcugh 12 in-of leakage paths due to assembling tolerances at :cp cf inle: down-comer and thirty 3/4 inch holes located a: the bottc of the therral shielu. No credit was taken for pessible leakace cf nitrogen directly to the hot-leg rupture /ia the cutle pipe slip jcint which separates the cutle; and inle: plenu: or the expansien volume which night be available in the cold-leg piping.
354 is continuing to analyce the ef f ects cf nitregen blevdewn and does not plan to dccument the analysis presented for the Unit 2 since it is not ccepleted.
3&4 was asked to consider in future analysis of this p*'
. the possibile effec:s of nitregen that could pass thrcugh
.te core in such a canner as :o blanket fuel pins.
It could then determine the maximum fuel pin clad te= eratures which cight occur on the basis of
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this conserva:ive assumption.
It indicated such an analysis would be considered.
4 Radiolvtic Hvdrecen 36W presented the current status of 1:s analysis of the radiclytic hydrogen ferred during the post-accident period following an LOCA.
The analysis indicated that the hydrogen concentration would be for ce=bustion (4.1%) in the cen-expected to reach thq) lower limit tainment (2 x 106f-volu=e at approxicately 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> af ter the accident occurred. The analysis considered three scurces for hydrogen:
(1) radioiv:1c decc pesition 3 0.3 =clecules/100 ev and an integrated dese of 1.7 x 100 R in three cenths, (2) 0.1% circonium-water reaction, and (3) chemical reaction.
3&W has reviewed three possible methods:
(1) venting, (2) inerting and (3) recc=biners, of centrolling the hydrogen concentration in the contain=ent. The presentation of the analysis using venting rates frc: 750 SC7H to 3000 SC7H starting a: different ti=es af:er the accident indicated that the hydrogen concentration is maintained below the 4.1% fla== ability li=it with the resulting taxinus of f site dose of less than 0.2 rec.
Although 3&W feels it could support ven:ing as a solution to the hydrogen problec, JCPL indicated it had not reached any conclusion as to hcw it would con:rol hydrogen in the containment and rculd indicate in the Unit 2 PSAR (answer to question 2.0, Radiclvtic Hverczen ueneration) that the evaluatica of ce:heds to be used is continuing.81-156
Roger S. 3 yd 5.
Centrcl Red Drive Mechanis-JCPL will include in A endmen: No. 5 cf the Uni
- 2 PSAR additicnal information to supper: the change tc the roller-nut drive rechanis:
in answer to Dr. P. A. Morris le :er Oc Mr. R.
I. Neidig, Metrcpolitan Idison Ccepany, dated' January 7, 1969.
6.
I: dine Receval JCFL indicated it intends to =eet Par: 100 on allowable dose l' nits u
by reducing the leak rate value and indicated its intent to leave roc: for ins:allatica of high efficiency filters or other iodine renoval systens if necessary.
S. h e,.u.,. e c
JCPL has indicated it will submit A=endment No. 6 on February 17, 1969.
It wculd like to =ake the May 1969 ACRS =eeting with issuance of the construction per=1: by mid-July 1969. We indicated : Sat this schedule was possible but could =ake no cc= itzen: to see: the schedule.
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Rav.nend R. ?cwell Reactor Project 3 ranch 2 Divisien of Reac:cr Licensing cc:
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A. Morris F. Schroeder a
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,ev.ne D. Skovholt R. DeYeung 3 ranch Chief s, DRL Cc=pliance (2)
D. Sullivan J. Sears 4 Nischan C. Moen
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Lis cf A :endees81-157 M
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2 AIC - ORL 3aScock i ~iilecx R. Tedesco G. Ward R. ?cwell W. A. Cchb D. Sullivan*
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E. 71cra J. Sears
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S. Little M. Wetterhahn*
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R. S=ith G. Lainas*
?. Howe" Jersev Central W. Nischan*
C. Mocn*
J. ". Neely M. Resen*
J. Smith
- GPL' R. Mattsen*
- 3. G. Avers Cc=cliance R.
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Heward E. G. Rec =e J. Hendecson*
>LP R 3 urns L Roe N. M. Cole J. C. Archer I. H. Mandil S. A.
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Chapin Pickard & Leve
- . Wecdard
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81-158
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