ML19321A797
| ML19321A797 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse, Oconee, Arkansas Nuclear, Crystal River, Rancho Seco, Crane  |
| Issue date: | 10/24/1979 |
| From: | Capra R NRC - TMI-2 BULLETINS & ORDERS TASK FORCE |
| To: | Israel S NRC - TMI-2 BULLETINS & ORDERS TASK FORCE |
| References | |
| NUDOCS 8007240208 | |
| Download: ML19321A797 (1) | |
Text
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((gb Q)o, UN!TED STATES NUCLEAR REGULATCRY COMMISSION 2
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October 24, 1979 Docket Nos: 50-259, 50-270, 50-287, 50-289, 50-302, 50-312, 50-313, 50-346 MEMORANDUM FOR:
S. Israel, Leader Systems Group, B&OTF s
FROM:
R.A. Capra, B&W Project Manager, Project Management Group Mane, Acting Leader, Project Management Group, B&OTF THRU:
SUBJECT:
UPGRADE OF ANTICIPATORY REACTCP. TRIP - B&W OPERATING PLANTS By our letter to all B&W operating plant licensees, dated Septenber 7,1979, we requested that licensees review their schedule for installing the safety-grade anticipatory reactor trip for loss of feedsster and turbine trip. "e informed them that if the safety-grade trip could not be installed within approximately 6 months following NRC approval, they would have to upgrade the control-grade trip, as an interim measure, In addition, we requested licensees respond to the request for additional information enclosed with the letter.
We have received responses from all licersees (E.nclosures ' through 6).
All licensees, except TMI-1, state that they can meet the six months installation schedule. Answers to our RAI are also contained in the licensees' responses.
It is requested that Enclosures 1 through 6 be reviewed for acceptability.
Requested completion date is November 15, 1979.
Please contact me at X-27745 f f additional information is needed.
Enclosures:
1-Duke Power Co. Itr of 10/05/79 n
2-AP&L 1tr of 10/08/79 CC L 3-SMUD 1tr of 10/05/79 R.A. Capra, B&W Project Manager 4-FPC itr of 10/02/79 Project "anagement Group 5-TECO ltr of 10/03/79 Bulletins & Crders Task Force 5-Met-Ed ltr of 09/28/79 cc:
D. Ross T. Novak W. Kane D. Thatcher 8007240208 m
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272.. css October 3, 1979 Mr. Earold R. Denton, Director Office of Nuclear Reactor Re3ulation U. S. Nuclear Regulatory Cc=nission Washington, D. C.
20555 f Attenti:n:
Mr. R. W. Reid, Chief Cperating Reactors 3 ranch 04 Re: Ocenee Nuclear Station Docke: Nos 50-269, -270, -287 sar Sir:
-s a let:er dated May 21, 1979, a system design descriptien for a safety grade anticipatory reac:or trip on turbine trip or less of cafs feedvater was subnitted for Ccenee Nuclear S:ation.
his was I
frovided pursuant to my letter of April 25, 1979, Mr. W. S. I.e e 's letter of April 26, 1979, the NRC Crder of May 7,1979, and II Eulletin 79-053.
Subsequently, in a letter da:ed September 7,1979, the NRC srsif reques:ed additional infor=ation in order to approve the c:n,p:ual safety grade design. Attached please find our response :: '. 12 request.
Of particular concern to the staff was :he lengthy lead ti:: 'cr Cur'ently, it is anticipa:ed : hat naceria". - _; he installation.
r available en site for installa:icn vi:*..in sin nenths of ; i.;., ;-:cval of the design. Equipnen: that can be ins:alled with '-* " '
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entire nodificatico vill be ce=pleted on each uni: the firI
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--- k ARKANSAS POWER & UGHT CCMPANY x,
PCST CFRCE eCx 551 UTTLE RCCX. AFKANSAS 72903 (5C1) 371- 000 October 8, 1979 l-109-8 Director of Nuclear Reactor Regulation ATTN: Mr. R. W. Reid, Chief Operating Reactor Branch #4 U.S. Nuclear Regulatory Commission Washington, D.C.
20555 I
Subject:
Arkansas Nuclear One-Unit 1 Cocket No. 50-313 License No. OPR-51 Anticipatory) Reactor Trips (File:
1510 Gentlemen:
Cur letter of May 21, 1979, provided a conceptual safety-grade design for initiating reactor trips upon loss of main feedwater and/or turbine trip. Your letter of September 7,1979, requested additional information ngarding our proposed design. This letter provides the requested informa-I tion.
As indicated in the enci: sed respon:es, our schedule for equipment procure-ment allcws implementation of the safety-grade design within approximately six (6) menths of NRC a;:p~Jval. Therefore, no proposed improvements in the current control-grade trip are necessary as your safety-grade schedule car, be met.
Very truly yours, bO.) Y$
David C. Trimble Manager, Licensing CCT:C21:nak Atta:5. ment piM M 'N E
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Floricia P,.o. w...e.r October 2, 1979 File:
3-0-3-a-3 Mr. Robert W.
Reid, Chief Operating Reactors Branch No. 4 Division of Operating Reactors U.S. Nuclear Regulatory Cocaission Washington, D.C. 20535 f
SU3 JECT: Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Dear Mr. Reid.
On September 19, 1979, Florida Power Corporation received your letter dated Septe=ber 7,1979 requesting cddi:ior.al infor:ation concerning the upgrade of the anticipatory reactor trips on turbine trip er loss of =ain fee / water at Crystal River Unit 3.
l You specifically requested Florida Power Corporation to provide the additional infor:ation identified in the enclosure of your le:!er anc evaluate the possibility of improving the installation schedule for the safety grade anticipatory trips previously identified in our response to IE Bulletin 79-05B.
In that regard, enclosed is our response to I:e=s 1-9 identified in the enclosure of your letter.
Our previous i:ple:entation schedule for this design :odification was approx 1:ately 12 :onths following NRC approval of our proposed desi;n.
This schedule was based on the long lead ti=es necessary for :he
=snufacture, delivery and installa: ion of safety grade equipment.
As indicated in our response to Ite: 5, we have been able to locate so e existing qualified equipment from a utility who is experiencing delays in cons:ruction of its nuclear plant.
These cocponents can be delivered to the tigg g ' g y g g y @ g *'M % % SIK3/ M 7l]
C".!)3 within 22 weeks fro:
The installation of this equip e re:ueling outage or outage of su ;,
DUPLICATE DOCUMENT f ol' owing receipt of :he equip:e '
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License No. NPF-3 LCWELL E. EcE vc.m.u.m Serial No. 540
....o..c...ue.n wu 2n us2 October 3, 1979 Director of Nuclear Reactor Regulation Attention:
Mr. Ecbert W.
Reid, Chief Operating Reactors 3 ranch No. 4 Division of Operating Reactors United States Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Reid:
This letter is in response to your September 7, 1979 request for addi-tional information on the upgrading of the anticipatory reactor trip system (ARTS) at the Davis-Ecsse Nuclear Power Station, Unit 1 (DB-1).
Toledo Editon is designing and purchasing an ARTS which will be separate from the Babcock and Wilcox reactor protection system.
'Ihe original de-sign was submitted on May 21, 1979 (TECo letter Serial No. 1-71).
Since that time the design has been nodified to incorporate recent reactor trip experience.
Details are provided in tha attached response to item 6 with the enclosed revision 1 to Bechtel Co. Drawing No. SK-E-410.
The modifications provide improved testability and remove a low reactor power block signal.
The revised design only blocks the turbine trip signal below 207 power.
Loss of feedwater signals remain effective at all power levels.
In order to expedite as much as possible the installation of the safety grade trip system, Toledo Edison has already issued the design for vendor bids.
If there are no changes in the proposed system as a result of the NRC design review, the schedule may be able to meet your requested ic-proved installation date of six months af ter NRC approval. At this time such an improvement is tenuous and cannot be committed to.
In lieu of that assurance, attachment A provides an identification and discussion of a modification to the interim ARTS sy,stemgphmc.o%LggmidgMN y~ 7pp q six months of your concurrence.
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y Very truly yours, DUPLICATE DOCUMENT i
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writer > o. rect o.at %e oer Septaber 28, 1979 GOL 1218 2259.1.2 Director of Nuclear Reactor Regul.* tion Operating Reactor Branch d4 U. S. Nuclear Regulatory Commission Washington, DC 20555 At t ent ion:
R. W. Reid, Chief
Dear Sir:
SU3 JECT: THREE MILE ISLAND NUCLEAR STATION UNIT 1 DOCKET No. 50-289 LICENSE NO. DPR-50 ANTICIPATORY REACTOR TRIP UPGPR ING Your letter concerning the subject reactor trip requested that Met-Ed provide infor=ation on any improvements pr oposed for the control grade trip in the
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event that it could not be upgraded to safety grade within about 6 conths.
Met-Ed plans to install the B&W proposed safety grade trip system at TMI-1.
Discussions with B&W indicate that the delivery ok eqt '.pment necessary to implec:ent the design may not be ccasistent with TMI-1 restart.
In order to provide a high quality trip system prior to startup we plan to upgrade the trip system that is described in the TMI-1 Restart Report (Sect ion 2.1.1.1).
The upgrading will include at a minimum redundancy of sensors and logic as well as a provision for testability. The details of the uegrading will be provided with a future amendment to the Restart Report.
In addition, the safety grade trip system that will replace the control grade system will be described in Section 2.1.2 of the Restart Report.
Responses to the nine questions in the enclosure of your letter will be provided as well.
Very truly yours,
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(9 b.Lb5 J. G. Herbein Vice Presidene ec:
H. Silver D. DiIanni 10, 0 0 5 0 T9's-Y P
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