ML18089A552

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Forwards plant-specific Info on Reactor Protection Sys Shunt Trip Mods,In Response to NRC & Generic Ltr 83-28. Shunt Trip Mechanism Will Be Installed During Refueling outage.W/14 Oversize Drawings.Aperture Cards in PDR
ML18089A552
Person / Time
Site: Salem  PSEG icon.png
Issue date: 03/14/1984
From: Liden E
Public Service Enterprise Group
To: Varga S
Office of Nuclear Reactor Regulation
References
GL-83-28, NUDOCS 8403290281
Download: ML18089A552 (14)
v • d • e


Text

-

OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department March 14, 1984 U. s. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Licensing Washington, D.C. 20555 Attention:

Mr. Steven A. Varga, Chief Operating Reactors Branch, No. 1 Gentlemen:

PLANT SPECIFIC INFORMATION ON RPS SHUNT TRIP MODIFICATIONS SALEM GENERATING STATION UNITS NO. l AND 2 DOCKET NOS. 50-272 AND 50-311 In our letter dated July 15, 1983, Public Service Electric & Gas (PSE&G) committed to incorporating a shunt trip function into the automatic trip circuits of the Reactor Protection System (RPS).

These modifications will be achieved using the generic design developed by Westinghouse for the Westinghouse Owners Group (WOG).

The generic design was reviewed and accepted by ONRR in a letter to the WOG dated August 10, 1983.

Attached to the August 10, 1983 letter were thirteen questions to be answered by each utility in order to define differences between the generic and plant specific designs for licensees using the WOG design.

Accordingly, enclosed is our response to the 13 plant specific questions.

In answering these questions, PSE&G believes that the enclosure also provides the plant specific design information required by Generic Letter 83-28, Section 4.3 and is hereby submitted for your approval.

We are planning to install the shunt trip mechanism in Unit 1 during the current refueling outage tentatively scheduled to be completed August 1, 1984.

Your prompt review and approval of 1'~ 8403290281 840314 PDR ADOCK 05000272 P

PDR The Energy People 95-21 68 (80 M) 11-82

u. S. Nuclear Regulatory Commission 3/14/84 the design to support this schedule would be appreciated.

cc:

Mr. Donald c. Fischer Licensing Project Manager Mr. James Linville Senior Resident Inspector Sincerely, Liden Manager -

Nuclear Licensing and Regulation

ENCLOSURE RESPONSES TO THE 13 PLANT SPECIFIC QUESTIONS REQUIRED BY NRC PRIOR TO IMPEMENTATION OF THE DESIGN MODIFICATION TO PROVIDE AUTOMATIC ACTUATION OF RT BREAKER SHUNT TRIP ATTACHMENTS.

1.

Request for drawings Please find the electrical schematic/elementary diagrams for the reactor trip and bypass breakers showing the undervoltage and shunt coil actuation circuits and breaker status information/alarms to the control room.

The drawings for Unit No. 1 are the attached bluelines numbered:

203613-ABL-547-IR-1EC1628-C5/0 203614-ABL-547~IR-1EC1628-C6/0 240111-B-9653-IR-1EC1628-C7/0 240148-B-9654-IR-1EC1628-C8/0 232011-B-9795-IR-1EC1628-Cll/O 232412-B-9795~IR-1EC1628-Cl2/0 SH.2 221051-B-9545-IR-1EC1628-Cl6/0 The drawings for Unit No. 2 are the attached bluelines numbered:

203613-ABL-547-IR-2EC1638-C5/0 203614-ABL-547-IR-2EC1638-C6/0 240111-B-9653-IR-2EC1638-C7/0 240148-B-9654-IR-2EC1638-C8/0 232011-B-9795-IR-2EC-1638-Cll/O 232412-B-9765-IR-2EC1638-Cl2/0 221051-B-9545-IR-2EC1638-Cl6/0 Please note that these are interim drawings and will not be formally released until NRC approval of the proposed design is received.

DG7 1/6

r

  • ,. 2.

Request for Class lE Power with Indication and Overvoltage Capabilities 2.A. POWER SUPPLIES The 125 volt control power supplied to the reactor trip breakers meet Class lE requirements.

The power source for the "A" reactor trip breaker is from the "A" 125 volt battery system while the "B" reactor trip breaker is from the "B" 125 volt battery system.

A description of the 125 volt battery systems may be found in the UFSAR Section

8. 3.

Since the Class lE circuitry provided to the shunt trip is separated from Non-Class lE circuitry per criteria in effect at the time of licensing, and as further addressed in the FSAR, credible faults within Non-Class lE circuitry will not degrade the shunt trip function.

2.B. INDICATION DG7 2/6 The main control board is equipped with a red light which indicates that the breaker is closed and a green light which indicates that the breaker is tripped.

Under normal conditions the red light will be "on" steady.

This lamp is operated "on" normally by a supervising relay that is installed in the breaker 125 volt D.C. control circuit.

The relay is installed in series with the breaker shunt trip coil and a breaker auxiliary contact.

If the breaker is closed, the relay will be energized and will light the red lamp on the control board which indicates that power is available to the shunt trip device and that there is continuity through the shunt trip coil.

The proposed design will add an alarm function such that if the 125 volt D.C. power is lost or continuity through the shunt trip coil is lost, the supervisory relay will de-energize and operate a main control board alarm.

The added main control board alarm will cause a yellow alarm light to flash in the section of the main control board in which the breaker closed light is installed and an audible warbling tone will be initiated.

The console lights are powered by the 28 volt D.C. battery system which is similar in design to the 125 volt D. C. battery system which is also described in Section 8.3 of the UFSAR.

2.C. OVERVOLTAGE CONDITIONS The added shunt trip circuitry relay is powered from the reactor protection system power supplies.

There are two power supplies in the solid state protection system and the auctioneered high power supply normally supplies the load.

If an overvoltage condition exists (115% of nominal 48 VDC), the power supply supplying the load will turn off and the redundant supply will pick up the load.

A control room overhead annunciator will alarm a general warning for the particular train due to the loss of the power supply.

If an overvoltage condition still exists, the redundant power supply will also remove the load.

Circuit malfunctions resulting in an overvoltage condition will result in load removal which is a fail safe condition since load removal will de-energize both the u. V. coil and the added shunt trip activation relay.

3.

Request for Information on Added Relays PSE&G has received information from the vendor that the relays are within the capacity of the SSPS power supplies and that the relay contacts are adequately sized for the shunt trip function.

The added relays will be Potter Brumfield MDR Series, Westinghouse part No. 955655.

These are the relays specified in the NRC approved Westinghouse generic design.

DG7 3/6

... 4.

Request for test procedure proposed by WOG PSE&G has reviewed the WOG procedure and determined it to be compatible with the design configuration at Salem 1 and 2.

The sequence of steps used to independently verify operability of the undervoltage and shunt trip devices in response to an automatic reactor trip signal will be identical to the procedure proposed by the WOG.

5.

Request for Class lE Shunt Trip Function The added circuitry to be used to implement the automatic shunt trip function will be Class lE.

The design is in accordance with the design bases as described in the Salem UFSAR Section No. 7 except that power is required to operate the shunt trip coil.

The procurement, installation, operation, testing and maintenance of this circuitry will be in accordance with PSE&G Salem quality assurance procedures which satisfy the quality assurance requirements of Appendix B to 10CFR Part 50.

6.

Request for Seismic Qualification The WOG is working with Westinghouse to obtain seismic qualification of the shunt trip attachments.

The balance of the added circuitry will be seismic class I.

All non-safety related circuitry/components in physical proximity to or associated with the automatic shunt trip function will not degrade the trip function during or after a seismic event.

7.

Request for Environmental Qualification PSE&G has information provided by the vendor that the components to be used to accomplish the automatic shunt trip function are designed for the environment in which they are located.

8.

Request for Separation Physical separation will be maintained between the circuits used to manually initiate the shunt trip functions of the redundant reactor trip breakers.

A description of the main control console reactor trip switches is in the UFSAR Section 8.1.4.2.5.

The shunt trip interposing relays and reactor trip logic outputs will be mounted in separate metal enclosures.

All of the field cabling from the main control board and the DG7 4/6

.. reactor protection logic to the redundant Train A and Train B reactor trip switchgear will be routed separately as Train A and Train B circuits.

All associations with non safety grade equipment will be through coil to contact isolation.

9.

Request for Test Procedure of Control Board Manual Switches The operability of the control room manual reactor trip switch contacts and wiring will be adequately tested prior to startup.

The test procedure will not involve installing jumpers, lifting leads, or pulling fuses.

The test procedure will verify the independent operation of the undervoltage and shunt trip circuitry.

10.

Request for bypass Breaker Testing Although there may be some benefit to reactor trip system reliability associated with frequent testing of the bypass breaker, the benefit is of questionable value.

Bypass breakers are closed only during testing of main trip breakers and it is only during this time that the bypass breaker could be called upon to provide a protective action.

Testing occupies in total, approximately 12-18 hours per year per train or 0.14%

to 0.21% of the operating time of the reactor trip system per year.

Testing the bypass every 18 months results in an unavailability value of 3.2 x lo-3.

Finally, the purpose of the bypass breaker is to allow on-line testing of the reactor trip system.

Protection is still considered to be provided by the opposite train main trip breaker.

A situation which would require action by the bypass breaker would include:

Condition

1.

One train in test

2.

Requirement for Reactor Trip

3.

Failure of Main Trip Breaker Probability of Occurrence Per Year 12/year 3.5 x lo-4 The occurrence of such a situation is 8.4 x l0-6 per DG7 5/6

1

  • year.

Considering that bypass breaker unavailability is 3.2 x 10-3, the probability of complete failure of the reactor trip system during testing is remote and does not appear to warrant frequent testing of the bypass breakers.

Thus, based upon our analysis, we believe there is no need for bypass breaker testing.

11.

Request for Reactor Trip Breaker Operability Indication Test Procedure Test procedures to be used to verify the operability of the reactor trip breakers will demonstrate the proper operation of control room indication/annunciation pertaining to the status of the breakers.

12.

Request for Response Time Testing Test procedures used to verify the operability of the reactor trip breakers will be revised to include the response time of the automatic shunt trip feature.

The test procedures which will include the automatic shunt trip time response will be the monthly functional test and the 18 month time response tests.

13.

Request for Technical Specification Changes Refer to Attachment "A" for proposed Unit No. 1 Technical Specification changes and Attachment 11 B 11 for Unit No. 2 Technical Specification changes.

These will be verified and formally submitted for approval following installation of the shunt trip mechanism.

TLP:jab DG7 6/6

ATTACHMENT II A II

'I I* -

TAUU 4.3-1

'I c

llEACTOll TIUP SYSTEM INSTHUMENTATION SURVE IL!:_A_t!~!!~!l~l-~~~l~MJ:N IS

  • --.o:

~

CllANNU MODES IN Wiii Cll t

CllANNEL rtJNCT I ONAL SUltVI: 11.l l\\Nt[

F UNC Tl ONAL UN IT CllECK CALIBRATION TEST

__ 1_~E_tll! ~ n~_u __.

1. Manual lleactor Trip Switch N.A.

N.A.

S/U{9)

N.A.

I

2.

Power Range, Neutron Flux s

0(2), M(3)

M l, 2 and Q(6) *

3.

Power nange, Neutron Flux, High Positive Rate N~A.

R(6)

M 1

  • 2
4.

Power Range, Neutron Flux, CJ lligh Negative Rate N.A.

ll(6)

M l

  • 2 i::.

LJ

5.

Intermediate Range, I

Neutron Flux s

ll(6)

S/U(l) 1

  • 2 and *

.~

.~

6. Sburce ltange, Neutron Flux 5(7)

R(6)

M and S/U(l) 2, 3 *. 4. 5 and A

7.

Overte1111*erature £\\ T s

~ ll M

1

  • 2 U.

Overpower fl T s

n M

l

  • 2

~-

PressuriLer Pressure--Low s

It M

1

  • 2 e
10. Pressurizer Pressure--tligh s

I~

M 1

  • 2
11. Pressurizer Water Level--High s

R M

l

  • 2 l l. Loss ot flow - Single Loop s

n M

I PAGE 1-3

c:

z

-1 l..J

~*

l..J

  • N TAULE 4.3-1 {Continued)

REACTOR_TIUP SYSHM INSTRUMENTATION SURVEILtANCE _!!! q~!~~~t~t NI S CllANNll FUNCTIONAL UNIT

13.

Loss of Flow - Two Loops

14.

Steam Generator Water Level--

Low-Low

15.

Steam/Feedwater Flow Mismatch &

low Steam Generator Water Level

16.

Undervoltage - Reactor Coolant Pumps

17. Underfrequency - Reactor Coolant Pumps
18.

Turbine Trip

a.

Low Autostop Oil Pressure

. b. _Turbine Stop Valve Closure

19.

Safety Injection Input from SSPS 20.-

Reactor Coolant Pump Bredker*

Posit ion Trtp

21.

Reactor Trip Breaker

22. Automatio Trip Loyic CtlANNEL CHECK s

s s

N.A.

N.A.,

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

CALI DRAT ION R

R R

R N.A.

N.A.

N.I\\.

N.A.

N.A.

N.A.

FUNCllONAI.

HSl N.A.

M M

M M

,. S/U( I)

S/lJ( l)

M(4)

I~

S/U( IO), M( ll) and SA(l2)

M( 5)

HODES IN Wit I Cit SUllVE I U.AHCE

__ __!!!.!l'!!_l!_ED __.

I

1. 2 9 I
  • 2 I

l l

  • 2
1. 2
1. 2 e N.A.

I, 2 and*

l. 2 and,.

PAGE 2-3

1-NOTATION

( 1 )

( 2)

( 3 )

( 4)

( 5)

( ~)

( 7)

( 8)

( 9)

( 10)

( 11)

  • e TABLE 4,3-1 (Contintied)

With the reactor trip system breakers closed and the control rod drive system capable OF rod withdrawal.

If not performed in previous 7 days~

Heat balancP. only, above 15~ of RATED THERMAL POWER.

Co~pare inccre to excore axial offset above 15~ of RATED THERMAL POWER.

Recalibrate if absolute ~ifference ~ 3 percent.

Manual SSPS functional input check e~ery 18 months.

Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS.

Neutron detectors may be excl~ded fro~ CHANNEL t~LIBR~TIO~.

Below P-6 (Block of Source Range Reactor Trip) setpoint.

Logic only,_ if not performed in previous 92 days.

If not performed in the previous* 24 hou~s, conduct a functional test of the Manual Reactor Trip Switc~es to v~rify the Manual Reactor Trip Switch and the independent operation of the u.v. and shunt trip wiring.

If not performed in the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, conduct a functional test of:

Perform a functional test of:*

  • Reactor Trip Breaker u.v. Trip and Shunt Trip (via SSPS) and conduct response time testing of u.v. and Shunt Trip/Breakers (event recorders)

( 12)

Perform periodic maintP.nance on Reactor Trip ~reakers and Reactor Trip Bypass Breakers semiannually as follows:

a.

response time testing, (3 times) {visicorder) trend data

b.

trip bar lift force measurements

c.

u.v. output force measurement

d.

dropout voltage check

e.

servicing/librication/adjustments (See Table 3.3-1 Notation###)

f.
  • repeat testing steps {a-*d) following any necessary actions a*t step (e)

SALEM -

UNIT 1 nr.;

~. 1 3/4 3-13

.PAGE 3-3

I.

c :z -

-i N

- ATTACHMENT "B" TABLE 4.3-1 REACT OIL!!~ IP SYS HM I NSTRUHENTAT I ON_ SURVI~ !_I! ANCl J~I q~_!l!~_M_l _NI S_

Ctll\\NNI I FUNCTIONAL UNIT

1.

Manual Reactor Trip Switch

2.

Power Range, Neutron Flux

3.

Power Range, Neutron Flux, High Pos1t1ve Rate

4.

Power Range, Neutron flux.

High Negative Rate

5.

Intermediate Range.

Neutron Flux

6.

Source Range. Neutron flux

7.

Overtemperature 8 T

8. Overpower fl T
9.

Pressurizer Pressure--Low

10.

Pressurizer Pressure--lligh

11.

Pressurizer Water Leve 1--li i gh

/

12.

Loss of flow - Single Loop CtlANNEL CHECK N.A.

s N.A.

N.A.

s S(7) s s

s s

s s

CAL I BRAT ION N.A.

0(2), M(3) and Q(6)

R(6)

R(6)

R(6)

R(6)

R R

R R

fUNC r I ONJ\\L HST S/U (9)

M M

M S/U(l)

Mand S/ll(l)

M M

M M

M M

\\

  • ~

HOOE S IN Wiii Ctl SUltVlltLANCE

__ ltEl}U I UEO __

N.A.

l

  • 2 l
  • 2
l. 2 l
  • 2 and
  • 2
  • 3. 4
  • 5 and "

l

  • 2 l
  • 2 1
  • 2 l
  • 2 l
  • 2 1

PAGE il-3

c :z

-t N

LJ I.......

N TADtE 4.3-1 (Continued)

~~EACH~!~. TR IP SYSTEM I NSTIWHENTATION SURVU LLANCE _ _!!_t!IU lltlM_~:~L~

CllANNf t FUNCTIONAL UNIT

13.

Loss of Flow - Two Loops

14.

Steam Generator Water Level--

Low-Low

15.

Steam/Feedwater Flow Mismatch &

Low Steam Generator Water Level

16.

Undervoltage - Reactor Coolant Pumps

17. Underfrequency - Reactor Coolant Pumps
18.

Turh1ne Trip

a.

Low Autostop Oil Pressure

b.

Turbjne Stop Valve Closure

19. Safety Inject ion Input fro111 SSPS
20. Reactor Coolant Pump Breaker Posit ion Trip
21.

Reactor Trip Breaker

22.

Automatic Trip Logic CHANNEL CHECK s

s s

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

,N.A.

CALI BRAT JON R

R R

R R

N.A.

N.A.

N.A.

ll N.A.

N.A.

FUNCllONAI.

TEST N.A.

M M

M M

1 S/U(l)

.. S/U(l)

M(4)

S/lJ(O)

S/U ( 10). M( 11) and SA( 12)

M(5)

MOUES IN WHICll SllHVE It LANCE

_ __fil!)U 1 llEO ____ _

1. 2 l
  • 2 1

1 N.A.

N.A.

e*

    • 2 e l

1, 2 and

  • l, 2 and
  • PAGE 2-3

NOTATION

. ( 1)

( 2)

( 3)

( 4 )

( 5)

( 6)

( 7)

( 8) -

( 9)

TABLE 4,3-1 (Continued)

With the reactor trip system breakers closed and the control rod drive system capable OF rod withdrawal.

If not performed*in previous 7 days.

Heat balance only, above 15% of RATED THERMAL POWER.

CoMpare incore to excore axial offset ahove 1511; of RATED THERMAL POWER.

Recalibrate if absolute difference ~ 3 pel:'.'cent.

Manual SSPS functional input check e"9ry* 18 months.

Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS.

Neu~!:'.'On detectors may be excluded fro~ CHANNEL CALIBRATION.

Below P-6 (Block of Source Range Reactor Trip) setpoint.

Logic only, if not performed in previous 92 days.

If not performed in the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, conduct a functional test *of the Manual Reactor Trip Switchai to verify the Manual Reactor Trip Switch and the independent operation of the u.v. and shunt trip wiring.

(10)

If not performed in the previous ~4 hours, conduct a functional test of:

(11)

Perform a functional test of:

  • Reactor Trip Breaker u.v. Trip and Shunt Trip f via SSPS) and conduct response time testing of u.v. and Shunt Trip/Breakers (event recorders)

(12)

Perform periodic maintenance on Reactor rrip Rreakers and Reactor Trip Bypass Breakers semiannually as follows:

a.

response time testing, (3 times) (visicorder) trend data

b.

trip bar lift force meas4rements

c. u.v. output force measurement
d.

dropout voltage check

e.

servicing/librication/adjustroents (See Table 3.3-1 Notation###)

f.

repeat testing steps (a-d) following any necessary actions at step (e)

SA.LEM -

UNIT 2 DG7 3_._l 3/4 3-13.

_P_A_G_E_3-3 j

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