ML20113D694

Forwards Response to Conditional Items Per 841108 SER on Generic Ltr 83-28,Item 4.3 Reactor Trip Breaker Automatic Shunt Trip. Addl Info Justifying Addition of Status Lights for Bypass Breakers Also Encl

ML20113D694
Person / Time
Site:	Beaver Valley
Issue date:	01/14/1985
From:	Sieber J DUQUESNE LIGHT CO.
To:	Varga S Office of Nuclear Reactor Regulation
References
GL-83-28, TAC-53166, NUDOCS 8501230192
Download: ML20113D694 (9)

Text

.

sh des

'A@

ouquesneumt ..p _ _

Nucle r DMalon SNppingport. PA 150774)04 January 14, 1985 U.S. Nuclear Regulatory Commission Division of Licensing Attn: Steven A. Varga, Chief Operating Reactors Branch No.1 Division of Licensing Washington, DC 20555

Reference:

Beaver Valley Power Station, Unit No 1 Docket No. 50-334, License No. DPR-65 Safety Evaluation Report on Generic Letter 83-28. Item 4.3 Gentlemen:

By letter dated November 8,1984 you provided the Safety Evaluation Report (SER)~ for Generic Letter 83-28, Item 4.3, Reactor Trip Breaker Auto-matic Shunt Trip, based on our July 16, 1984 submittal.

The SER concluded that the proposed modification is acceptable, condi-tional on the following items:

- Adding bypass breaker position status lights on the main control board Confimation of seismically qualified shunt trip components Testing of the bypass breaker shunt trip attachment prior to bypassing a reactor trip ':reaker Testing of the bypass breaker position status lights Revised Technical Specifications for bypass breaker testing and independent testing of the shunt and undervoltage trip attachments on the reactor trip breakers The Beaver Valley 1 response to each of these items is attached. As noted, we are providing additional information to justify our position on adding status lights for the bypass breakers since they are not required for a control room operator to readily determine the status of the bypass breaker position. Moreover, these status lights are not considered a requirement of the WOG generic design if certain other design features are-available.

The testing of the reactor trip and bypass breakers on a bi-monthly frequency is perfomed during the bi-monthly testing of the Solid State Protection System (SSPS) since the SSPS must be used to-initiate the trip-signal to the undervoltage coil. The present Technical Specifications only allow one train of the SSPS to be out of service for two hours. The additional testing _ being required as part of Generic Letter 83-28 has raised concerns on the feasibility of performing all the tests within the time f d\

8501230192 850114 PDRADOCK05000g

\

January 14, 1985 Beaver Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66

. Safety Evaluation Report on Generic Letter 83-28, Item 4.3 Page 2 limit. Therefore, we recommend that this issue be considered prior to imposing additional test requirements and that the NRC program for enhancing Technical Specifications (NUREG 1024) along with the reviews of WCAP-10271

.(WOG TOPS) be expedited.

If you have any questions, please contact my office.

Very truly yours,

. D.

Senior Manager Nuclear Group Attachments cc: Mr. W. M. Troskoski, Resident Inspector U.S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U.S. Nuclear Regulatory Commission c/o Document Management Branch Washington, DC 20555 Director, Safety Evaluation and Control Virginia Electric & Power Company P.O. Box 26666 One James River Plaza Richmond, VA 23261

1 Beaver Valley 1 Response to NRC Safety Evaluation Report on Generic Letter 83-28, Item 4.3, Automatic Shunt Trip Modification NRC Condition 1;(a) Submission of revised information including revised electrical schematics showing provisions of bypass _ breaker position status lights on the main control board as noted in Item 1.

Response

Bypass. breaker position status lights on the main control board are not required

> for the control room operator to readily determine the status of the bypass breakers or considered a requirement of the WOG generic design.

1. Vestinghouse'has reviewed our configuration and found it acceptable. -

2. The schematics provided _with the WOG generic design package.were

" typical" of Westinghouse plants' and were provided to show the interconnection of the undervoltage trip attachment, shunt trip panel, and shunt trip attachment.

~

3. Due :to the sheer number of different indicating lights in,the control room,- the' bypass breaker status lights would not alert the operator to -

the change in breaker status without an alarm. However, an alarm already exists with the annunciator circuit.

S- 4. The time that .a' bypass breaker may. be .In' service is' limited by

< Technical Specifications. Currently, one bypass breaker is in service-

. for less than two~ hours per month.

5. The . hardware configuration will not permit'both bypass breakers to be-

-racked in-at the same time.

6. Racking Lin cand closing aL bypass breaker will?cause the'following "

-control room annunciation with annunciator horn:

~

.

• L A4-101 " ROD DRIVE POWER BUS BYPASS BKR :1A CIDSED"'

OR 6

• CA4-109 " ROD DRIVE POWER BUS BYPASS BKR 1B' CLOSED"

~

r s - ;

L*'DA4 3 75 m" REACTOR-PROTECTION. SYSTEM TRAIN A TROUBLE"^ ' '

I R:

O e-

' * ?A4-83 '? REACTOR-PROTECTION SYSTEM TRAIN BITROUBLE"

~

Y

$ f

> ' 1-

-e:

, , c . . -. - - . - . . - -. - .. -_ . . .

7. Racking in and closing as bypass breaker will cause the following

. control' room indication: '

la . Plant Computer (P-250) Points:

i

• Y0026D "REAC AUX TR BKR A" OR

• Y0027D "REAC AUX TR BKR B"

b. Sequence-of-event Recorder Points:

• 192 " ROD CONT BYP BKR A CLOSE" OR

• 201 " ROD CONT BYP BKR B CLOSE"

• 167 " REACTOR PROTECTION SYS TRAIN A TROUBLE" OR E~'178 " REACTOR PROTECTION SYS TRAIN B TROUBLE"

]

c. The Group- Light'oon the Plant Variable Computer System (PVS)

- console will. flash. Pushing the Group Button displays the; state of the points 'in the' group (16 points / group). -In addition, the

PVS.alerm printer will record the change of state.

r-.

l8. The_ bi-monthly . tests of the. reactor protection system (MSPs 1.04 and

~1.05) verify proper operation of annunciators A4-101 and A4-109, .P-250 points .Y0026D 'and Y0027D, and sequence-of-events points 192 and 201 when a bypass breaker is closed and opened.

' 9. Th's -availability of space on the main control board neartthe reactor.1 trip breaker contro1~ switch, 1-RTC, is limited to an area.of 5-1/2" x

-4el/2". If bypass breaker position ~ 11. hts' are added, Lthis area _ may not'_-

be. sufficient for all eight lights (i.e., 'A' Trip . Breaker- open and

'M' _

closed, 'B' Trip Breaker open and closed, 'A' Bypass Breaker open and-

_ closed,B' Bypass Breaker open and closed). -Therefore, --the bypass

, breaker position lights would have to :be located'elsewhere on-the;

' control board which may not provide'the capability.to-readily determine.

~

.the_ status of the reactor trip system.

110. Conservativel costa estimates; for : adding .the ~ indicating lights are Lapproximately,$35,000 and the change is not cost effective.

~

m l

{

U - ,

-.m_ t. _ ..

11. The status of' breaker position for the trip and bypass breakers is not required in the emergency procedure since a reactor trip is verified by the rod bottom lights. A reactor trip failure would be detected by:

• No rod bottom lights

• No decrease in neutron level on the nuclear instrrmentation

• Increasing RCS pressure, RCS temperature, pressuitzer level, Steam Generator pressure, and decreasing RCS sub;ooling Based on the above, it is not credible that a bypass of the reactor trip breaker or a SCRAM failure can occur without indication in the control room. Therefore, additional modifications to the main control board and associated circuits to provide for bypass breaker position status lights are not justified.

NRC Condition (b) Confirmation that shunt trip components have been seismically qualified as noted in Item 6.

Response

The WOG is working with Westinghouse to obtain seismic qualification of the shunt trip attachment and auto shunt trip panel. The Westinghouse report on the cyclic and seismic testing is not expected to be issued until March 1985.

NRC: Condition (c) Confirmation that testing of bypass breaker undervoltage trip attachments will be performed as noted in Item 10.

Response

Note,. Item 10 of the safety evaluation report requires testing of the shunt trip attachment; therefore, this item should reference shunt trip attachment instead of-the undervoltage trip attachment.

MSPs 1.04 and 1.05, " Reactor Protection Logic System Train 'A' ('B') Bi-Monthly

' Test," have been revised to test the shunt trip attachment- of- the bypass.

' breaker, with the breaker in the test position, via the local trip pushbutton prior to closing for reactor trip breaker testing. This verifies that the shunt trip attachment will_ open .the bypass breaker.

NRC Condition (d) Confirmation that bypass breaker testing will demonstrate proper operation of-control- board bypass breaker position . indication as identified in Item 11.

Respor.se The bi-monthly itests of' the reactor -protection system (MSPs 1.04 and 1.05) verify proper operation of annunciators A4-101 and A4-109, P-250 points Y0026D and Y0027D, and sequence-of-events points 192 and 201.

p L _ .

Since 'the ~ addition of bypass breaker position lights is not being pursued at this time, there are no plans for testing position status lights.

NRC Condition

'(e). Submission of proposed Technical Specifications noted in Items 10 and 13, following implementation of this modification.

Response

Attached are . proposed Technical Specification changes for Beaver Valley 1.

1These will be verified and formally submitted for approval following installation of the-shunt trip modification and onsite review.

Functional Unit 24- and Note 10 are proposed for incorporation of the bypass breaker testing requirements as indicated in Item 10 of the November 8, 1984 Safety Evaluation Report.

Independent verification of the undervoltage and shunt trip attachments required by Item 11 of the November 8, 1984 Safety Evaluation Report is proposed for Functional Unit 21 during the Channel Functional Test by Note 11 on a bi-monthly frequency.

A

. . ~. . - .,

~ !i

.. p

~

. l Tall!E 4.3-1 '

RFJCIOli 'lllIP SYSTfM INS'ITHfNPATIQI SilINElIJAIEE RIUlIlu2ENTS f', OIAIRIVI. FI7)ES IN HIIIOl

' GINSET. GIAIREL Fl!!CTIGIAI. SUINEII.IANCE ,

i.i 11tK.';'IGIAI. ItllT OllrK CAI.IllRATIGI TE!If IllUlIltED '

g

{

.l- 1. ilii.iuil ik:.ictor Trip H.A. .N.A. S/lJ(1) N A.

i.

2. I't w r Ituvyt, Ibutron Flux

, a. liigh Selpoint S D(2), M(3) H 1, 2

.u. anxl Q(6)

• 8

,, b. Izu Setpoint. S N.A. S /11 ( 1 ) 2 l'iwr Ituvys, Ib'utron Flux, H.A.

i ., 3. '

R H 1, 2 2 Iligin Ibsitivo Ibte Y 4 Itwr lusvje, Ibutron Flux, N.A. R. Il 1, 2 l* 111 9 1: Negative lute .

5. Intermediate Ibrvje, S ' ll. A. S/ll(l), H(7) 1, 2, 3 * ,

Ibutron Flux 4*,5*

i- 6. Source Ibiwje, Ibutron Flux N.A. *

', N.A. S/II(l), Mill) 2, 3*, 4*

M (D

liblow 1*-10) azul 5*

7. ther taircrature T S H H - 1, 2

" fl . Oven pr wr .T

, S R 11 1, 2

~

A. P-6 N.A. H.A.

M(9) 1, 2 1

11 P-8 H.A. H.A.

t M(9) 1 .

C. P '8 N.A. I II. A. M(9) 1 D. P-lO tl. A. II. A. M(9) 1 E. P-13 II. A.

H II(9) I A L Reactor 7%p Bjfah3 N. A. M. A M(sjo) and s/tt(s)' I,1.*

B<ea ker3 '

i.

9 l - -

i

-,=-- 4,3-1 (cd,_i,.. g -

/ .

, lorcat -

h'i'$ the react == trip system bre.=.kers c1csed and 9.e c:nt:ci .[j

=d drive system capable of cd wit.Y.::ro.l. .

fi I

. (1) -

If rc: ; '-+ in p sricc.s 7 dzys.

j (2) -

• de2.t M.'"'Oe C".1 7 p ahCve 15% Cf . 'T 052% M9 i .

I (3) -

Ccccare ir.c::e to e:c:=re a.v4 =1 1:ta'ance aheve 15% cf PA.r .

mys ps a =n,u- . an yer;fy ofERA8L E /be ,

. shunt rc:,a A Hac4 meat y;a, the iscs/ pasf Au tron.g

. wI th fE e .brea)cef ln Yhd fesi fos l Non fr;or to clo. sin 9 & A,eecfor Tr$ Brea Aer Tss7%f.

i.

N (Il} ~ T]t e cflA NN51 i~uptc7ECNAL T'Es T o*f fl.e R ede Y '

Trip Bres kerJ .S'b 4 h /erlff on$efe//daa~f ofER ABELZTy af ffe un d'ervoHoje and .54unt hy A Hsc4m <i e t.c.

• d o' C.'. U . *.- * *- ." '.-* ~ "

. 3/4'2 '3 Ar.end: en: .',':. 32 M-.

^

jp _ .pe.e.+ .p+ g *Ve-**"'?.