ST-HL-AE-2115, Forwards Proposed Tech Spec Change for Slave Relay Test Exemptions & Justification for Change,For Info & Use.Change Requires Slave Relay Testing Only in Plant Modes When Plant Operating Condition Would Not Be Adversely Affected

Forwards Proposed Tech Spec Change for Slave Relay Test Exemptions & Justification for Change,For Info & Use.Change Requires Slave Relay Testing Only in Plant Modes When Plant Operating Condition Would Not Be Adversely Affected

ML20209D164
Person / Time
Site:	South Texas
Issue date:	04/22/1987
From:	Wisenburg M HOUSTON LIGHTING & POWER CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
ST-HL-AE-2115, NUDOCS 8704290194
Download: ML20209D164 (13)

Text

..

The Light Company. . . _ _ . _ . _ , _ _ _ . _ _ . -

n<,,,si ,,, uyi>uiix & i>.,m i .o. am im n<><>si,,, . w,, 7mi m m.nu April 22, 1987 ST ilL-AE-2115 File No.: G9.06 10CFR50.36 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 South Texas Project Unit 1 Docket No. STN 50-498 Proof and Review Technical Specification Chant.es Attached for your information and use is Houston Lighting & Power's (IIL6P) proposed change for slave relay test exemptions, as well as justification for this proposed change. This change requires slave relay testing only in plant modes when the plant operating condition would not be adversely affected. Please note that the proposed change is similar to the exemptions granted at Shearon llarris and Callaway Nuclear Plants.

If you should have any questions on this matter, please contact Ms.

Frostie A. White at (512) 972-7985.

M. R. W senburg Deputy P oject M tager FAW/1jm Attachments

)( p L3/NRC/dp a

g) s/

I

llouston 1.ighting & Power Company ST-HL-AE-2115 File No.: G9.06 Page 2 cc:

Regional Administrator, Region IV M.B. Lee /J.E. Malaski Nuclear Regulatory Commission City of Austin 611 Ryan Plaza Drive, Suite 1000 P.O. Box 1088 Arlington, TX 76011 Austin, TX 78767-8814 N. Prasad Kadambi, Project Manager A. von Rosenberg/M.T. liardt U.S. Nuclear Regulatory Commission City Public Service Board 7920 Norfolk Avenue P.O. Box 1771 Bethesda, MD 20814 San Antonio, TX 78296 Robert L. Perch, Project Manager Advisory Committee on Reactor Safeguards U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue 1717 H Street Bethesda, MD 20814 Washington, DC 20555 Dan R. Carpenter George Smith Senior Resident Inspector / Operations Westinghouse Electric Corp.

c/o U.S. Nuclear Regulatory Monroeville Nuclear Center Commission Northern Pike P.O. Box 910 Monroeville, PA 15146 Bay City, TX 77414 J.D. Shiffer Claude E. Johnson Vice President Senior Resident Inspector /STP Nuclear Power Generation c/o U.S. Nuclear Regulatory Pacific Cas & Electric Company Commission 77 Bealo Street, Room 1445 P.O. Box 910 San Francisco, CA 94160 Bay City, TX 77414 Dr. W.R. Corcoran M.D. Schwarz, Jr. , Esquire Advanced Light Water Reactors Baker & Botts Program Office Director One Shell Plaza Combustion Engineering, Inc.

Ilouston, TX 77002 1000 Prospect 11111 Road Windsor, CT 06095-0500 J.R. Newman, Esquire Newman & lloltzinger, P.C.

1615 L Street, N.W.

Washington, DC 20036 T.V. Shockley/R.L. Range Central Power & Light Company P. O. Box 2121 Corpus Christi, TX 78403 L3/NRC/dp J

ATTACHMENT / -

. ST-HL AE d//S 3 PAGE / OFI

a. :

Revised Technical Specification Pages for

• Solid State Protection System (SSPS) Slave Relay Test Exempt

~

ns , ,,,

Several slave relays are actuate-tested from the SSPS; plant upset or' adverse impacts on plant operation would result from testing of these slave' relays , _

during certain plant modes. Therefore, HiAP requests that these slave ' relays be tested in accordance with the attached marked-up Technical Specificacions. -

Justification for this change is provided in Attachment 2. ' '

N s s-

• Note: Other changes affecting this hble.have not been included on this markup.

• y 4lP' s

b T

k *

~\, . -

q ,

t  % .c k,

s +

\

~%

P M*

V T k

7 r 4-L3/NRC/dp

- P ;.

r . <, ,

ATTACHMENT /

s TABLE 4.3-2 ST.HL.AE-4//f .

PAGE_f) OF I

$ ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 3! SURVEILLANCE REQUIREMENTS i h TRIP

$; ANALOG ACTUATING MODES

. CHANNEL DEVICE MASTER SLAVE FOR WHICH c_ CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE g FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED H

1. Safety Injection (Reactor Trip, Feedwater Isolation, Control Room Emergency Ventilation, Start Standby Diesel Generators, Reactor Containment Fan Coolers, and Essential Cooling Water)

$ . a. Manual Initiation N.A. N.A. N.A. R N.A. N.A. N.A. 1, 2, 3, 4

b. Automatic Actuation N.A. N.A. N. A. N. A. M(1)  !:(1) Q (c,h 1, 2, 3, 4 Logic and Actuation Relays

c. Containment Pressure- S R M N.A. N.A. N.A. N.A. 1, 2, 3, #

High-1

d. Pressurizer Pressure S R H N.A. N.A. N.A. N.A. 1, 2, 3 Low

e. Compensated Steam Line S R M N.A. N.A. N. A. N.A. 1,2,3 Pressure-Low

f. Compensated T -

S R M N.A. N. A. N. A. N.A. 1, 2, COLD 4

Low - Lota .

g

,c3

. t i

l r .-

I ATTACHMENT /.

l

. ST.HL-AE J//S l

TABLE 4.3-2 (Continued)

PAGE a OF f

, m 8

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION .

$ SURVEILLANCE REQUIREMENTS w

Q '

TRIP

$; A. "_0G ACTUATING MODES

. CHANNEL DEVICE MASTER SLAVE FOR WHICH c- CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE i g FUNLfIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED

" 2. Containment Spray

a. Manual Initiation N.A. N.A. N.A. R N.A. N.A. N.A. 1,2,3,4

b. Automatic Actuation N.A. N.A. N.A. N.A. M(1) M(1) Q 1, 2, 3, 4 Logic and Actuation .

Relays

. $ c. Containment Pressure- S R H N.A. N.A. N.A. N.A. 1,2,3 w High-3 I

N

3. Containment Isolation

a. Phase "A" Isolation

1) Manual Initiation N.A. N.A. N.A. R N.A. N.A. N.A 1, 2, 3, 4

2) Automatic Actuation N.A. N.A. N.A. N.A. M(1) M(1) Q(8) 1, 2, 3, 4 Logic and Actuation Relays

3) Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.

b.f.ContainmentVentilationIsolation

1) Manual Initiation lot ICk ICk

• M- h h I 2' '- #

S*2'hm2 M and 3.a.1 Q % ed, 'n%Y'on suddlance. rTi tements.

s g PROOF & REVIEW COPY 4

e

- /

l ATTACHMENT /

ST.HL AE- J//I TABLE 4.3-2 (Continued) _ PAGE V OFI ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION .

2 SURVEILLANCE REQUIREMENTS h TRIP

$; ANALOG ACTUATING MODES

, CHANNEL DEVICE MASTER SLAVE FOR WHICH

c. CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE z FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED

• 5. Turbine Trip and Feedwater Isolation

a. Automatic Actuation N.A. N.A. N.A. N.A. M(1) M(1) qui) 1, 2, 3 e-Logic and Actuation Relays w b. Steam Generator Water S R H N.A. N.A. N.A. N.A. 1, 2, 3 e-Level-High-High (P-ly) 2

c. Compensated T cold -L w 5 R M N.A. N.A. N.A. N.A. 1,2,3

d. Feedwater F1ow-High S R M N.A. N.A. N.A. N.A. 1,2,3 Coincident with either

of the following in 2 of 4 loops

Reactor Coolant Flow-Low or T,yg-Low

e. Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.

f. T -Lo[C?1;.L.. 5 R H N.A. N.A. N.A. N.A. -1, 2, 3 avg wh M r-Tri,4  %

Qo

6. Auxiliary Feedwater x N.A. 1,2,3 2;;;

a. Manual Initiation N.A. N.A. N.A. R N. A. N. A.

4

b. Automatic Actuation N.A. N.A N.A. N.A. M(1) M(1) Q 1,2,3 o and Actuation Relays Q

ATTACHMENT '

. ST-HL-AE- 4/'I

PAGE S OF #

TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION

j SURVEILLANCE REQUIREMENTS

--e R D asirn L. TRIP R ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR WHICH c CHANNEL CHANNEL CHANNEL z OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED

~

11. FHB HVAC (Continued)

c. Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.

d. Spent Fuel Pool Exhaust Radio- S R. M N G. N. 4 N . R. d. A. u,g ;Q;d,)

activity-High g ,,

R . .

k\ poo g TABLE NOTATION (1) Each train shall be tested at least every 2 days on a STAGGERED TEST BASIS.

(a) 44tm wh %snnq % oxauAel b chuwd CdA Mon.

CD w% pcuer greuter h er e %L Ao 4ne. We<\ocX seYpoht,-%. n piired oPmN6L TES y o g ,*Tr*sk all co d a t cQ v $ i i -%d- % bted oc,l( is gn -4{ ;te]

5+"te M h *- Pd"Ove canundstor Adm 3 c o n n m m tic e o, comeyr c4 ,,,Aw hs g;,% c,m_A.

Co w eAumke< r A h q (O %AUdon and ad 3wbeE o{ -Mp se4 pdidst cot ce -

ired.

l o O

THIS PAGE OPEN PENDING RECEIPT OF INFORMATION FROM THE APPLICANT m 12 m

. k N be M kbY OM K M Gnb b P69 (Unm1644C 'Q enQ, d1 a w w.w a [%\numw 6ok)p c,-e G31, QMf

%dn cotb WTW exce A q M k m ,s, ,\ew weu 6, nwwpma tai

% w e_ b eer. h teb w h A g

• C (3) e 4 <-W( AckM be. tegg'ah'S,g gj e

~

~

ATTACHMENT 2 ST.HL-AE 4/T PAGE / OF I Justification for SSPS Slave Relay Test Exemptions y The proposed change to the Proof and Review Technical Specifications requires 4

that seven slave relays have their test . intervals lengthened to at least every 18 months during refueling and during extended cold shutdowns. Additionally, it is proposed that the slave relay for the accumulator discharge isolation valve be tested quarterly, but only when the accumulator would not inject the accumulator contents into the reactor coolant system, i

l Each of these slave relays actuates one or more devices. The attached table t

lists each of the devices actuated by the slave relays. Justification is also 1 provided in the table for not actuating the device, as applicable to the devices.

1 The slave relays employed in the STP Solid State Protection System are used in other recently licensed Westinghouse plants. The performance history for these relays, based upon information available, has been excellent.

Additionally, the slave relays proposed for these lengthened test intervals

, are identical in design to the other slave relays in the SSPS. Because a relatively small percentage of the total number of relays fall into the lengthened testing interval category, there is a high probability that a failure due to a generic design defect or application will be discovered during the quarterly tests of the other slave relays.

I We also note the following related testing performed at STP. The master relay testing verifies continuity to the slave relay coil. With the exception of valves noted on the attached table (valves tested at intervals other than quarterly per the ASME Section XI Pump and Valve program), those components

actuated by exempted relays will be tested on a quarterly basis. While this J test does not employ the slave relay output contacts, it does help ensure the I operability of actuated equipment. Individual system / component technical l specification surveillance testing is also performed.

4 The attached table details, for each relay suggested for special testing, the following information:

o relay number I

o equipment number - the equipment numbers of every piece of equipment I

actuated by the given relay o service description - a brief description of the function of each device

o test concerns - identifies the difficulties associated with i actuating specific devices 4

l

\

l L3/NRC/dp i

i 1

ATTACHMENT 5

- ST-HL-AE- 4 //f PAGE / OF# -

j EXEMPTED SLAVE RELAY TABLE ,

Page 1 of 5 1

Relay No. Component Service Description Testing Proposed & Test Concerns

! K807 a) FV-7151 Feedwater Bypass Control Valve Slave relay testing at least once i K814 FV-7152 per 18 months during refueling and (Feedwater FV-7153 during extended cold shutdowns.

. Isolation) FV-7154 Valves are actuated to the closed

! position.

Opening of the feedwater bypass control valves to verify closure on slave relay testing would result in

perturbing feedwater flow to the

steam generators, causing 1

undesirable power transients.

Relief was granted for these valves in the ASME Section XI Pump and l Valve Program.

4

! K815 a) XSI0039A Accumulator Discharge Isolation Valve ,

(SI Signal) XSI0039B Slave relay testing quarterly only '

XSIOO39C when RCS pressure is above 700 psig.

l j b) HHSI Pmp 1A High Head Safety Injection Pump Actuation of relay K815 results in HHSI Pmp 1B opening of the accumulator discharge HHSI Pmp IC isolation valve. Should this relay testing be required when the RCS c) Auto Recirc Auto Recirculation Safety Injection Latch pressure is less than 700 psig, the '

l SI Latch accumulator would discharge its i Train A,B,C contents into the RCS. This action would require refilling.of the d) FV-3936 RUST to SFPCCS Valve accumulators before power (Train A) ascension could continue.

3 FV-3937 (Train B) i L3/NRC/dp

ATTACHMENT 5 '

. ST.HL-AE R!!I panF J OF S EXEMPTED SLAVE REIAY TABLE ,

Page 2 of 5 Relay No. Component Service Description Testing Proposed & Test Concerns K829 a) FV-8565 Instrument Air Containment Isolation Valve Slave relay testing at least once (Containment per 18 months during refueling and Isolation b) FV-3651 PRT RMW Containment Isolation Valve during extended cold shutdowns.

Phase A)

Train B only c) FV-3652 PRT Vent Containment Isolation Valve Valves indicated are actuated to the closed position.

d) FV-2455 PASS RCS Sample Containment Isolation Valve FV-2455A Closure of the instrument air valve (item a) isolates instrument air to air operated valves inside contain-ment resulting in possible operation of the valves to their failure position. Valves, whose operation could affect the plant operation at the time of testing, include the letdown orifice isolation valves, pressurizer spray valves and air-operated RHR valves.

Relief was granted for this valve (item a) in the ASME Section XI Ptunp and Valve Program.

L3/NRC/dp

ATTACHMENT 3 ST-HL-AE- 9/15~ '

t PAGE 3 OF f EXEMPTED SLAVE RELAY TABLE ,

Page 3 of 5 ,

Relay No. Component Service Description Testing Proposed & Test Concerns K831 a) XCV0025 Charging Isolation Valve Slave relay testing'at least once (Containment (Train A) per 18 months during refueling and Isolation during extended cold shutdowns.

Phase A) *b) LCV-465 Letdown Stop Valve (Train A) Valves are actuated to the closed LCV-468 position.

(Train C)

Isolation of the charging flow to c) XCV0024 Letdown Containment Isolation Valve the RCS (item a) would decrease (Train B) significantly the capability of the XCV0023 CVCS to provide proper boration (Train C) ratio. The isolation would only

! allow a flow path. through the RCP

{ d) WLO312 Liquid Waste Processing System Containment seals which is a less effective (Train A) Isolation Valve (from RCDT) boration path. There would also be l FV-4913 pressure perturbations on the RCP *

(Train B) seals. Isolation of the normal l letdown path (items b and c) results e) FV-4920 RCDT Vent Containment Isolation Valve in additional thermal transients on (Train A) the regenerative heat exchanger.

FV-4919 Pressurizer level control is I (Train B) dependent upon the proper balance f of charging and letdown.

f) FV-3971 SI Check Valve Testing Containment (Train A) Isolation Valva Relief was granted for these valves FV-3970 (items a, b and c) in the ASME (Train B) Section XI Pump and Valve Program.

g) FV-3983 Accumulator Nitrogen Containment (Train A) Isolation Valve

• A design change is currently in process to remove this signal from LCV-465 and LCV-468; the same relay would then provide the signal to the letdown orifice isolation valves (Train A - CV0012; Train C - CV0013 and CV0014). Closure of these valves would result in letdown isolation.

! ATTACHMENT 9

l

. ST-HL AE. 2117 PAGE V OF f . ._

EXEMPTED SIAVE RELAY TABLE ,

Page 4 of 5 i

i I

Relay No. Component Service Description Testing Proposed & Test Concerns i,

K845 a) FV-7189 Steam Generator Preheater Bypass Valve Slave relay testing at least once ,

K852 FV-7190 Per 18 months during refueling and  !

j (Feedwater Fv-7191 during extended cold shutdowns.

i Isolation) W-7192 '

, Valves are actuated to the closed e i b) FV-7145 Feedwater Bypass Containment position.

! FV-7146 Isolation Valve j FV-7147 Opening of the SG preheater bypass FV-7148 valves (item a) during power operation to verify closure on

., slave relay testing would result

in hot main feedwater being j

] injected into the cooler AW lines and into the SG's. This would i cause thermal shock and possible ,

damage to the A W nozzles at the .

.) SG boundary. - I i

i Relief was granted for these valves

(item a) in the ASME Section XI

} Pump and Valve Program.  !

j 1

I I.

i i . _ - _ . _ _ _ _ _ _ _ _ _ _ _ - _ _ - - _ _ _ - _ _ _ _

ATTACHMENT 5

. ST-HL-AE #/'#

PAGE I OF S EXEMPTED SIAVE REIAY TABLE Page 5 of 5

%[

i Relay No. Component Service Description Testing Proposed & Test Concerns K854 a) XCV0113A VCT Outlet Valve Slave relay testing at least once (SI Signal) (Train B) per 18 months during refueling and <

XCV0ll2B during extended cold shutdowns.

Trains 3 and (Trai.. C) Exemption is requested for trains C only. B and C only.

b) XCV0113B RVST to Charging Pump Suction Valve (Train B) Actuation of items a and b causes XCV0112C the charging pump suction to switch (Train C) from the VCT to the RWST The addition of borated RWST water c) LHS1 Pmp 1B Low Head Safety Injection Pump results in unnecessary rod movement.

LHSI Pmp 1C Large thermal changes to the RCP-seals can result from the switch in suction, increasing the probability of RCP seal failures and clogging of the seal injection filters.

Boration of the RCS at power can easily result in violation of the Axial Flux Difference Specification (4.2.1) and increase the amount of radwaste to be processed. There is also some possibility of a rector trip resulting from the Al penalty to the OTsT trip setpoint.

Relief was granted for these valves (items a and b) in the ASME Section XI Pump and Valve Program,

- _ _ . . . . - . - . - - . - - . - _ . - - . . - - - , . - - _ , ~ - ,_ .-