ML19326C904
| ML19326C904 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/21/1978 |
| From: | Stello V Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19326C900 | List: |
| References | |
| NUDOCS 8004280830 | |
| Download: ML19326C904 (2) | |
Text
,,
~
NOTIGS IN f
Since all employees were separated lated peak clad temperature might provide for the necessary operator ac-4 in October 1976 during the existe nce exceed 2.200 F.
tions within the recuired time frate.
of an active certification; a new Mves.
Previotts small break analyses for That is, in the event of a small t'reak tigation would serve no purpose. Con.
B&W 177 fuel assembly (FA) lowered and a limiting single failure, rnrwal sequently, the investigation has been loop plants had Idertified 'he limiting action will be taken to begin opening terminated.
small break to be in the suction line of these valves within five minutes omt Slened at Washins t on.
D.C.
, his the reactor coolant pump. For this as.
have them fully opened.;.d an acts sumed break location all high pressure cuate flow split cbwnus within 19 20th ' lay of April 1978.
ECCS flow injected into the system mint.tes. The ana;y.ws perfonned by MARVIN f,f. l' OoK3.
would add to the reactor coolant in.
B&W assumed that the flow split m:s Direefor. QUrce of ventory once the coolant level de.
established at 650 seconds by operator Trrtde Adjitstment Assist 2nce, creased to the helg5t of the reactor action. We conclude that the analvvs
[FTt Doc. 'r8-11651 Filed 4 27.r8; 8:15 ?ml vesset nozzles. Recently. B&W con. are a reasonable approximation of the cluded thst previous analyses did not operator action that actually will be
[7590-01]
consider that some of the high pres. taken, provided specific procedures are rure injection (HPI) flow would be lost preca*ed and followed to assure such NUCLEAR REGULATORY if the break were located in the dis. action.
/
COMMISSION charge line. As a result, recent analy.
B&W has stated that a 0.1 ft.' dts.
ses have shown that the discharge line charge line break, with the aforemen.
(Docket No. So-3131 break is more limiting than the suc. tioned operator 'acti,ons. is the most tion line break.
limiting case. To arrive at th!s concht ARKANT AS POWER & tlGHT CO., ARKArISAs The Arkansas Nuclear One-Unit sion. B&W has performed analyses at HutttAR ONE-UMT f40. I No. L plant has an ECCS configuration break sizes of 0.5. 0.2. 0.1. and 0.04 it.'.
order for Modifkation of Licerse which consists of two high pressure in.
with and without the assumed opera.
jection O!PI) trains. Each train has a tor action. The results for a power of I
IfPI pump and the train injects into 2568 Mwt. which were obtained using The Arkansas Power & Light Co.
two of the four reactor coolant system an approved Appendix K model far (the lleensect. is the holder of Facility (RCS) cold legs on the discharge side blowdown. Indicate core uncovery f" Operating License No. DPR.51 sh!ch of the RCS pump. (There is also a about 250 seconds for the 0.1 f t.8 IHm authorizes the operation of the nucle-third HPI pump installed.) The two ing break. For this break size H i ar power reactor known ns Arkansas parallel HPI trains are connected but has conservatively estimated the rn
,Nu' clear One-Unit No.1 (the facility) are kept isolated by manual valves clad temperature to be approxim391y at strady reactor power levels not in (known as the cross-over valves) that 1.200 F; well below the limits of to are normally closed. Upon receiving a CFR 50.46(b).
excess of 2568 megawatts thert"at (rated power). The facility consists of safety injection signal the HPI pumps B&W has indicated the manner in a Babcock & Wilcox Co. designed pres-are started and valves in the four in.
which the calculational methods have surized reactor (PWR) located at the jection lines are opened. Assuming loss been revised and has indicated that 11censee's site in Pope County, Ark.
of offsite power and the worst single their revised calculations are wholly in failure (failure of diesel to start) only conformance with the requirementa of g
one HPI pump would be available and 10 CFR 50.46. However. B&W has not two of the four injection valves would In accordance with the requirements f ail to spen.
yet had the opportunity to fully pre.
of the Commission's ECCS Acceptance If a small break is postulated to sent the result of its calculations tn Criteria.10 CFR 50.46. the fleeruee the licensee for submittal to the NRC submitted on July 9,1975 an ECCS occur b,t the RCS piping between the staff, and the staff has accordingly RCS pump discharge and the reector evaluation for the facility. The ECCS vessel the high pressure injection flow not had the opportunity to fully assca performanca Submitted by the licensee the new calculations. Until the lierns-was based upon an ECCG Evaluation injected into this line (about half of ee and the staff have an opportunity the output of one high pressure to review the B&W revised calc';b Model develooed by the Babcoch &
pu'np1 could flow out the break. tions, the staff has recommended 'in t Wilcox Co. (B&W). the desf gner of the Nuclear Steam Supply System for this Therefore, for the worst cor. aination the lleensee has agreed, that operatlN of break location and single failure, conditions be lirrdted to a range in facility. The B&W ECCS Evaluation only one. half of the flow rate of a which ECCS performance for small Model had been previously foun<1 to single high pressure ECCS pump break conditions is less sensitive te conform to the requirements of the we.uld contribute to maintaining the specific calculation inputs.
Commission's ECCS Acceptance Crite. coolant inventory in the reactor vessel.
For this facility, with operation or ria.10 CI'R Part 50.46 and Arpen<!!x This situation had not been previously to 2311 Mwt. ECCS performance c K. The evnluation Indic sted that -ith analyzed and B&W had indicated that the limits set forth in the ficility's the limits specified in 10 CPR 50.46 culations for the limiting small brmk does not even result in core unces m Technical Specifications, the ECCS may be excee' d.
Ing, if appropriate operator action 1:
coollng performance for the fact!!!y B&W has sued that they have nna. properly taken (as described abme!.
would conform with the criteria con.
lyzed a spectrum of small breaks in thus providing a very substanMal talned in 10 CFR 50 M b) whlah the pump discharge line and have de-margin on peak clad temperat* re govern calculated peak clad tempera. termined that to meet the limits of 10 ture, maximum cladding oxbla tion. CPR 50.46. operator action is required below the limits of 10 CFR 50.46(b).
Therefore, until the staff has ha 1 maxirnum hydrogen generetion, cocia. to open the two manmst operated cros, the opportumty to fully assess th-ble geometry and long term cooling.
sover valves snd to manually align the B&W revised calculations. opera
- fen On April 12. 1978 B&W informed t'vo motor driven isolation valves the NRC that it had determined that which had failed to open. This would of the facility at the power level spect.
fled in this Order, and in accordatec in the esent of a small break LOCA on allow the flow from the one HPI pump with the operating procedu the discharge side of a reactor coolant to feed all four reacter cooint legs. fled in this Order, will assure that f pump. high p essure injecticn (IIPI) B&W has assumed that 30 Sercent of ECCS will conform to the perfor-flow to the core could be reduced the flow would be lost tr rough the Smewhat. Subsequent calcuhtfons in.
break and 70 percent would refill the 50.46(b). Accordingly, such limits pro-mance requirements of 10 Cru ated that in such a case the caMu. cere. The licensee hu committed to vide reasonable as
'h-
,r,
f rDMtAt peGl1 Trit, VOt. 43, NO. 83-FRIDAY, APtit 28. 1974 g p. b 8004280 830
I836i NOIICO
~
public health and safety will not be [7590-01]
For the Nuclear Regulatory Cn endangered. Upon notification by the mission.
NitC staff, the licensee committed to (Docket No. 50-2651 Groact tran, provide the staff with B&W's reeva.
Chief.
Operating Reacto" luation of ECCS performance applica.
COMMONWEALTH Enl50N CO. AND IOWA-ble to the !!censee's facility as prompt.
ILLINOl$ GA5 AND EtECTRic CO, Brcnch No. J. Dtrision cf Or eroting Recctors.
e ficd h re n. an su tec nimi specification reltilrfrg acproprl.
ate operating procedur~s to nraure re-The Nuclear Regulatory Commission [7590-01]
quired operator action Ti cheured (the Commission) ha.s issued Amend.
herein. Such procedures were de.
ment No. 34 to Facility Operating Lt.
O CM N* 3*3 scribed nnd the committnents etn.
cense No. DPR-30, issued to the Com-firmed by the licensee's letter of April METROPOLITAN EDISON CO. ET AL monwealth Edison Co. (acting for 17 1378 supplemented by letters dated Apr!! 21.1978. The staf f belic"es itself and on behalf of the Iowa.Illi-Grea' ins of RI*f F'om AS ME 5ecr% XI nois Gas and Electric Co.), which re.
Innervice inspection (Testing) Requimw -
that the licensee's action und-tha circumstances is appropriate and that vised Technical Specifications for cp.
In the matter of Metree h'.
this action should be confirmed by eration of the Quad Cities Station Edison Co., Jersey Central Pom NRC Order. Upon satisf actory compte. Unit 2 (the facility) located in Rock Light Co. and Pent.syhania Elec%
tion of our assessment of the rettsed Icind County.111. The amendment is Co.
evaluation, we will accoidinriy modify effective as of the date of issuance.
The U.S. Nuclear Regulatory re.
the authorization to operate the facili.
This amendment extends the allowa. mission (the Commiszton) has grM ty, ble period of reactor operation with relief from certain requiremenu c.
Loop 2A of the Containment Cooling ASME Code. Section X[. " Rules !
IV Mode of the RIIR System inoperable Inservice Inspection of Nuclear l'r Copies of the follozing d&ument f or 7 days beyond April 24,1978 pro.
Plant Components" to the I.b trc's are available for inspection bt the vided that a visual inspection is per-tan Edison Co. The rehef rth tt s Commission's Pub!!c doctiment lioom forme I daily to assure that.' proper the inservice testing prestam f(t t' at 1717 11 Street. Washington. D.C.
WVe nlignment and system integrity Three Mile Island Nxtear htb 20555, and are being pit &d ;n the is maintained in the "B" RHR loop.
Unit 2 (the facuity). located h D Comrn!mion's local public document The applic stion for the amendment phin County, Pa. The ASME Ced, i t -room at the Arkansas Polytech& Col.
complies with the standards and re.
quirementa are incorporated tw r f. '
lege. Runellville. Ark.
quirements of the Atomic Energy Act ence into the Commission's ruin..
(1) Irtters from M r.
Doimld A.
of 1951, as amended (the Act), and the regulations in 10 CFR Part 50. ~I L Rueter to Mr.. R. W. Reid Chicf Oncr. Cemmission's rules and regulations. relief is effective as of its date of i ating Reactors Branch No. 4. Unted The Commission has made appropri. ance.
April 17 and 21.1918, and from Mr.
Daniel II. Williams to Mr. R. W. Reid Pte findings as required by the Act and Relief is granted until the stm' the Commission's rules and regula. commercial operation from cam:'
dated April 21.1978.
Accordingly, pursua.nt to the Nrmic tions in 10 CFR Chapter I. shich are ance with certain inservice testina r Energy Act of 1954, as amcr* t ami sat forth in the license amendment. quirements determined to be irmr-the Commission s Rults and myula. l'rior public notice of th!s amendment cal for the facility because corrplian tions in 10 CFR Parts - and !3 /t tr w33 not required since the amendment would result in hardships and una c.
orderr d. That Facility Operatine LI.
does not involve a significant hazards difficulties without a compensa'.inc in r onsideration crease in the level of quality er safi' '
The Commission has determined The request for relief complies wri t Ilr th folio i sions.
that the issuance of this. amendment the standards and requirements of it (1)'As soon as possible. the licensee will not result in any significant envi. Atomic Energy Act of 1954, shall submit a reevaluation Tholly in ronmental impact and that pursuant ed (the Act), and the Commt;a!c i
conformance with 10 CFR 50.19 of to 10 CFR f 51.5(d)(4) an environmen-rules and regulations. The Ceimr.
ECCS cooling performance cr!culated tal impact statement, or negative dec. sion has made appropriate findires r in acco dance with the D&'.'.' Cvalua. laration and environmental impact ap.
sion,lred by the Act and the Comr,p nqu tion Model for operation with opernt. praisal need not ce prepared in con.
s rules and regulatio ts in 10 (
inc procedures describad in itA letters ticetion with issuance of this amend. Chapter I. which are set forth in 't of April 17.1978. and April 21.1973.
m ent.
letter granting relief. Prior pu':i -
C Until further authorizatien by For further details with respect to n tice f this action was not tra me the Commission. the power leM shall this action, see (1) the application for since the granting of this relief fr +
not excee! 2311 Mwt. and ASME Code requirements does net n amendment dated April 13. 1978 (2)
(3) Until further authorizttlon by Amendment No. 34 to License No.
m a sWcant hr6 con
- the Comm%sion. the licen.=ce shall op-DPR-30. and (3) the Commission's re.
erate in accordance t'.ith the proce-dures described in its letter of April lated Safety Evaluation. All of these omm n has WmN items are available for pub!!c inspec. that the granting of this relief s!!! r.
17, 1978, supplemented by ! citers dated April 21,1978.
tion at the Commission's Public Dccu. nsu in any signmcant eWmuw o
-tal impact and that pursuant to
- ment Room. 1717 H Street NW Dated at Bethesda, Mi thb 21st Woshington. D.C. and at the Moline fm day of April 1978.
et state e o neg t ve e i Pugile Library., 501 17th Street, 6 6 e y of item tion and environmental imrrt 7 For the Nuclear Remlatory Com.
^i pratsal need not be prepared in ce 3
mission.
Vieror. Smt.o. Jr..
addressed to the U.S. Nuclear Regula. nection with this action.
Director. Division of Opentling tory Commission. Washington D.C.
For further details with remcct Rcactors. O// fee of N.:cic rr Re.
.0f 55. Attention: Director. Division of this action, see (1) the letter from th-actor Regulation.
Operating Reactnrs.
Mctropolitan Edison Co. dated Jan My 3,1978, and (2) the CommisrAn -
(FR Doc. 78-11588 F11ed 4-27 78: 8:15 am)
Dated at Dethesda. Md this 21st letter to the Metropolitan Ediwn C day of April 1978.
dated April 21,1978.
ftCP At REGl5ftt, VOL 43. tIO. 834RIDAY, APtit 28, 1978