ML20062L164

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Clarifies 800528 Response to NRC 800312 Request for Addl Info Re Bypass & Reset of Engineered Safety Features.Use of Manual Override Feature for Safety Actuation Signal Does Not Cause Inadvertent Bypass of Any Other Actuation Signal
ML20062L164
Person / Time
Site: Vermont Yankee Entergy icon.png
Issue date: 01/15/1981
From: Rich Smith
VERMONT YANKEE NUCLEAR POWER CORP.
To: Ippolito T
Office of Nuclear Reactor Regulation
References
FVY-81-11, NUDOCS 8101200388
Download: ML20062L164 (14)


Text

.

- VERMONT Y AS l{ EE N UCLEAR POWER CORPOR ATI()N SEVENTY SEVEN GROVE STREET B.3.2.1

- RUTLAND, YERMONT 05701 FVY 81-11 REPLY TO ENGINEERING OFFICE 1671 WORCESTER RO AD FR AMINGH AM. M ASS ACHUSETT5 of 701 TELEPHONE 617-8 7 2 - e 100 January 15, 1981 United States Nuclear Regulatory Commission Wash in gt or. , D.C. 20555 c_

O Attention: Office of Nuclear Reactor Regulation g -

Mr. T. A. Ippolito, Cnief ,

't Operating Projects Branch #2 =llp ,

U [3-;'

Division of Licensing Q Q 'J.* 'S m ca

References:

(a) License No. DPR-28 (Docket No. 50-271) #E (b) Letter, T. A. Ippolito (USNRC) to R. L. Smith (VYNPC) ddec Maren 12, 1980 (c) Letter, R. L. Smith (VYNPC) to T. A. Ippolito (USNRC), dated May 28, 1980 Sub je ct : Response to NRC Request for Ad:iitional Information for Bypass ar.d Reset of Engineered Safety Features for Vermont Yankee

Dear Sir:

Reference (b) requested that Vermont Yankee provide the subject response, which was submitted to the NRC in Reference (c). Subsequent discussions with members of your staff and personnel from the Franklin Research Institute have resulted in an NEC request for further clarification of the information provicec in Reference (c). This clarification is provided in the enclosure to tnis letter.

We trust this information will be satisfactory; however, should you have any further questions , please contact us.

Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION c*-

R. L. Smith Licensing Engineer ,

RLS/kab Enclosure .

THIS DOCUMENT CONTAINS P00R QUAUTY PAGES 610 h00SB% f .

Sobiect: Response to telacon of 10/6/80 with the R C ( J . T .

. 5 3rd) a,d Franklin x= ;earch In st itut e (Ian Sary2nt) on Elactri

~ C.

Override /5/pass Aspects of ESF Systems Question 1:

Criterion 1 - All ESF safety actuation signal circuits which Itincorporatt has been manual override features have been reviewed.

determined that the use of a manual override feature for any safety actuation signal does not also cause the inadvertent bypass of any other actuation signal.

Criterion 2 - Refer to Ouestion 2.2.

Criterion 3 - It has been deternined that the use of each manual override (identified in 2.1) is annunciated in the plan:

control room. A manually initiated system level annunciation of each override is also provided in thc control room.

Criterion 4 - The containment ventilation system is not isolated upon a containment high radiation siFnal. No containment high radiation signal exists, however, a main steam line high radiation will initiate isolation of all main steam lines, main steam line drain, and reactor water sample lines, and reactor building ventilation exhaust high radiation signs; will initiate isolation of tne containment ventilation system. FSAR Section 7.3.4.7, paragraphs 2 and 13 describe the above in detail.

Criterion 5- The instrumentation and control systems provided to initiate the ESF are designed in accordance with the ~

safety design bases FSAR, paragraphs 7.3.3 and 7.4.:.

individual component qualifications will be addressed in the response to IE Bulletin No.70-015.

Criterion 6- This was addressed in the response to IE Bulletin No. 80-06, YAEC letter to NRC, WVY S0-SS, dated June 13, 1980.

Question 2:

(1) See Table 1.

(2) T'ne present design uses administrative controls and annunciation coupled with some physical features to prevent inadvertent operation of all manual bypass or override' features , identifiea in 2(1).

include keylock switenes and multiple step sequential manual

~

These actions, (See Tabic 11.

(3) In accordance with telecon of 5/14/80, between Mr. Vern Rooney (SRC) and Mr. Robert Smith (YAEC), only the prints for the purge and ven:

system were submitted. In accorcance with telecon of 10/6/F'. wit' the NRC and Franklin Research Institute, a new complete set of prints on ths system has been forwarded under separate cover. Tnir new set of prints supercedes the set of prints sent to the NRC on 5/28/80, YAEC letter WVY 80-82.

( '4 ) Tne ESF initiation, control anc power supG:. rcr t r we-s .

2r, accor:-ince witn FEAh paragrapns 7 3. ; ar -

Quality assurance stancarcs used for eacr. actuation sirr.a; art cocumented in Appencix D of tne Ver .cnt Yanr:ee FSAE.

Tne component qualification stancarcs are accressed in resper.se tc IE Balletins79-01A and 79-015.

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SHEET 4 OF 11 NGINEERED SAFETY FEATURES VALVES & DAMPERS CONTROL BYPASS / OVERRIDE ACTilATION

  • OMPONENT CIRCUITRY
  • FEATURES SYSTEM SAFETY FUNC~ ION SIGNAL SOURCE

)ESIGNATION 1283 Manual override V10-39A RilR Suppression Close On:

in MCR (Note 3)

Chamber Spray a) liigh Drvwell Pressure 1282 V10-308 Upstream Valves b) Reactor Vessel Low Water and Reactor Pressure Low Close On:

1276, 1277 Manual override RilR Inboard Injection V104tA a) liigh Drywell Pressure or in MCR (Note 3)

V10-31.B Valves b) Reactor Vessel Low-Low Water Level and Reactor Pressure Low Close On: 1310, 1311 No override V10-32 (Inboard) RHR Isolation valves a) Drywell liinh Pressure or 110R, 1309 V10-33 (Outboard) b) Reactor Vessel Low Water with V10-17 (Outboard) c) liinh Reactor Pressure on v10-18 (Inho,rd)

Shutdown Catboard Containment open on: 1273 No override V10-27A RilR 1272 (LPCI) Valvas a) Drywell liigh Pressure or V10-273 b) Reactor Vessel Low-Low Water &

Reactor Pressure Low Close On: 1274 Manual override V10-26A RilR Outboard Iniection 1275 in MCR (Note 3)

Valves a) Drywell liigh Pressure or V10-26B (Spray Isolation} b) Reactor Vessel Low Water and c) Reactor Pressi.re Low 1277 Manual override V10-34A RilR Suppression Chamber Close On: in MCR (Note 3) a) liigh Drywell Pressure or 1278 V10-3413 Spray Test Bypass valve b) Reactor Vessel Low Water Level and Reactor Low Pressure 1281 Manual override V10-38A RilR Suppression Chamber Close On: in MCR (Note 1) a) llinh Orywell Pressure or 1280 VlO-38B Spray Valve b) Reactor Vessel Low Water Level and Reactor Low Pressure 1285 No override V10-65A RilR lleat Exchanner Opens on:

a) lii gh Drywell Pressure or 1284 Vlo-65n (LPCI) By pa s s valves b) Reactor Vessel Low-Low Water &

Reactor Low Pressure

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O 1GINEERED SAFETY FEATURES VALVES & DAMPERS SilEET 8 0F 11

)MPONENT ACTIIATION CONTROL BYPASS /DVERRItsE

'SIGNATION

, SYSTEM SAFETY FUNCTION SIGNAL SoliRCE CIRCUlTRY -* FEATURES RV2-71A ADS Sys terr. Pres sn-c Open on 752 Manual override RV2-71B Relief Valves Coincident Signals of: 753 in MCR (Notos 1, 4 )

RU2-71C (Auto Blowdown a) Reactor Vossol 1ow-I,ow 117 0 754 RV2-71D Fvstem) h) Drywel1 Ilinh Pressure 755 c) Core Spray or RllR Pump On D-12 ilVAC Isolation Valvo Close on- 1429, 1479A liigh radiation signal D-ll ( Commn Inlot) a) ReactSr Vessel Low-1,ow Water 1410 manual override in h) Drvwoll High Pressure MCR ( for either 1 of 2 c) liigh Reactor ill d g . Vent signals only)

Radiation or Re fuel Floor (Note 3) li i gh Ra li at ion R-7 SGT Drywel1 & Torus Close on: 1111 liinh radiation nignal (PCIS) Vent to Reactor a) Reactor Vossol Low-1,ow Water manual override in Building Exhaust h) Drywell Iligh Pressure MCR ( for either 1 of 2 Svatom Valvo c) lii gh Roactor Il l d g . Vent signals only)

Radiation or Rofuel Floor (Notos 2, l)

Iligh Ra<lin t inn n9 ITVAC niccharge Isolation Close on: 1429 liigh rad iat ion signal R-10 Valvos a) Reactor Vescol Low-Low Water 1479A manual override in h) Drywell liigh Pressure 1410 MCR (for oithor 1 of c) lii gh Reactor Hldg. Vent signals only) (Note 3)

Ra tl i ci t i on or Rofool Floor lii gh Radiat ion Open on: 1430 liigh radiation signal a) Reactor Vessel Low li7') manual ovorri lo in

R-?A, R SGT Exhaust Fan Water lovel MCR. ( for eitner 1 ol Isolation Valve - b) Drywell liigh Pressuro 2 signals only). Fan inlet c) liigh Reactor Bldg. Vent control mano.il ove r r i<
n-M , R Exhaust Fan Radiation or Rofuol Floor in MCR. (hot e 3)

Isolation Valve - lii gh Rad ia t ion Ontler Valvos actually initiat e<l by Exha u s t f ein s ; fans are in i t i.it od by abovo sinnals

SilEET 9 0F 11 INEERED SAFETY FEATURES VALVES & DA5tPERS CONTROL . BYPASS /DVFRRIDE ACTUATION tP0i1Eii r CIRCUITRY FEATURES

1CNATION SYSTEM SAFETY FUNCTION SIGNAL SollRCE 1430 tiich Radiation signal

-1A, B 4GT Isolation Valvo Open on: manual override in a) Reactor Vossol Low Water 1479 (Common Tnlet) MCR (for eithor 1 of 2 Level h) Drywel l ili ch Pressuro sinnals outv) (Note 3) c) lii gh Reac t or Bldg. Vent Radiation er Refool Floor IIigh Rad lat ion Closes on:

Manual override Recire. Recirculation Pump in MCR (fo- t e s t in g) 2-53A 1) llinh Drywell Pressure or 716, 717 P-51B System Discharco Valves (Noto 1) b) Reactor Vossol Low-i.ow W..r or Level &

Roactor Low Pressure Manual override

'2-54A Recire. Recirc. Pump Disch. C

_ lose on: 712, 711 in f1CR (for t e s t in g)

Bypass Valvos a) liigh Drvwell Pressure or

'2-54B Systen h) Reactor Vessel Low-Low Water 6 (Noto 1)

Reactor how Pressure Recire. Recire. Ma n i fol d Close on:

12-66A a) liigh Drywell pressure or 718, 719 Mein ua l override Svstom Cross-Tio Bvpass

'2-66B in PfCR (for t est ing)

Valves h) Reactor Vessel Low-Low Water &

Reactor 1.ow Pressure (Note 3)

Recirc. Recirc. Loop Close on:

!-39 111R 1,ow MSI. pressure 2-40 System Sample Valvo a) Reactor Vessel 1.ow-Low 1120 b) liigh Radiat ion MSL bypass whou made (pCis) switch not in run.

c) lli flow - Normal & Startup Startup raugo rango d) Low MSL Pressure bypassed i, run low e) Condenser I,ow Vacuum vacuum h v p.i s s in mode switen positions f) MSI. Arna Temporatoro IliPh other than run.

( f;o t o s 1, ? , 1)

R R 1

C C 1

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I PI G MS - O - O N OE US GS I. CR l.$D V. F 1

Valves and Ds-n.*rs Sheet il of 11 Encin . re i Safetv Featurer:

NOTES:

(1) Keylocked switch.

(2) Two or more sequential switch actions required.

(3) Bypass / override actions are administrative 1y controlled by operating procedures, technical specifications, and/or plant directives (includinz access restriction).

(4) Switch is remotelv or awkwardly placed to minimize or prevent inadvertent operation.

s 6m-. __ _ _ _ .