ML20199L016

Comments on SPDS SER .Outstanding Issues Identified in SER Being Addressed Consistent W/Schedule Identified in

ML20199L016
Person / Time
Site:	Hope Creek
Issue date:	04/08/1986
From:	Corbin McNeil Public Service Enterprise Group
To:	Adensam E Office of Nuclear Reactor Regulation
References
NUDOCS 8604100277
Download: ML20199L016 (4)

Text

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m Meill, Jr.

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April 8,

1986

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m Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission

-m 7'3 2 0 No:- f o lk Avenut Bethesda, Maryland 20614

'M Attention:

Ms. Elinor Acie n s am, Director Project Directorate 3 Division ut BWR Licensing D+ >a r Ms. Adensam:

SAFETY PARAMETER DISPLAY SYSTEM (SPDS)

SAFETY EVALUATIUN REPURT REVIEW HUPE CREEK GENERATING STATIUN DUCKET Nu.

50-334 Public Sirvice Electric and Gas Company (PSE&G) has revtowed the Sa t t > t y Eva l l it ion Hoport (SER) pertaining to the Hope Creek SPUS as aacumented in a lutter trum E Adensam (NRC) to C.A.

McNet11 (PSEsG) datod March LM, l '3 8 6.

The following comments a r, applicible.

l.

Delete first paragraph on page 7 of the SER bast d on the following:

m doth CRIDS and the Radiation Munitoring System (RMS)

"M calculate thu average suppression pool temperature.

Eight RTDs per chennel are included in the average and an average is ca lcu l a t e<l for each channel Each individua1 tomperature va)ue and ca1cu1ated average C

1. s transmttted frum the R"U to CHIDS.

The, temperature Y

values are validated by the RM-80 comput e rs prior to data transf er to CRIDS.

This va licia t i on includes a range check.

If al1 RTDs are functioning and in range, the RMS calculated average is displayed on CR1DS/SPDS.

g If any RTDs in a channe1 fai1 (1nc1uding out -of -range )

m the HMS calculated average for that channel t ra nsmi tte<l to CRIUS goes to zero (0)

When this occurs, CRIDS uses its calculated average ba s et t upon "N"

number of in range temperatures, this valao is displayed on the g

bPDS.

Inct i vid ua l RTD tallures vi'l be t ransmi t ted to the centra 1 refiation p r oce s.ci r but w111 not be sent to CHIDS.

8604100277 860408

@l PDR ADOCK 05000354 gkg F

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e Public Service Electric and Gas Company Ctrbin A. McNeill, Jr.

Pubhc Service Electnc and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609339-4800 vice President -

Nuclear April 8, 1986 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Attention:

Ms. Elinor Adensam, Director Project Directorate 3 Division of BWR Licensing

Dear Ms. Adensam:

SAFETY PARAMETER DISPLAY SYSTEM (SPDS)

SAFETY EVALUATION REPORT REVIEW 110PE CREEK GENERATING STATION DOCKET NO. 50-354 Public Service Electric and Gas Company (PSE&G) has reviewed the Safety Evaluation Report (SER) pertaining to the Hope Creek SPDS as documented in a letter from E. Adensam (NRC) to C.A. McNeill (PSE&G) dated March 18, 1986.

The fol.'owing comments are applicable:

1.

Delete first paragraph on page 7 of the SER based on the following:

Both CRIDS and the Radiation Monitoring System (RMS) calculate the average suppression pool temperature.

Eight RTDs per channel are included in the average and an average is calculated for each channel.

Each individual temperature value and calculated average is transmitted from the RMS to CRIDS.

The temperature values are validated by the RM-80 computers prior to data transfer to CRIDS.

This validation includes a range check.

If all RTDs are functioning and in range, the RMS calculated average is displayed on CRIDS/SPDS.

~

If any RTDs in a channel fail (including out-of-range) the RMS calculated average for that channel transmitted to CRIDS goes to zero (0).

When this occurs, CRIDS uses its calculated average based upon "N" number of in range temperatures, this value is displayed on the SPDS.

Individual RTD failures will be transmitted to the central radiation processor but will not be sent to CRIDS.

8604100277 860400 C>Sl PDR ADOCK 05000354 gg{

F pne

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i Director of Nuclear 2

4-8-86 Reactor Regulation i

I 2.

Delete reference to Validyae Multiplexers on page 9 of the SER.

The Validyne Ilultiplexers have no interface l

with the SPDS.

3.

Amend item 5 on page 13 as shown in Attachment I.

1 j

In addition, PSE&C notes that the outstanding issues identified

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in the SPDS safety evaluation report are being addressed 1

consistent with the schedule identified in a letter from C.A. McNeill (PSE&G) to E'. Adensam (NRC) dated December 26, 1985.

In the event there are any questions with respect to the above, do not hesitate to contact us.

j f

Sincerely, f

I i

C D.H. Wagner USNRC Licensing Project Manager R.W.

Borchardt i

USNRC Senior Resident Inspector I

5 1,

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ATTACHMENT'l Insert A (a)

Agastat Type GP, Model EGP-B001 (tested but not used)

(b)

Allen Bradley Type P, Model 700-200 A12P (Class 1E) Model 700-P200Al, (non-Class lE tested)'

(c)

Potter-Brumfield (P&B) Type MDR,' Model 4134-1 (d)

Struthers Dunn (SD), Model 219XBX245NE (Class lE) Model 219XBXP, 120VDC,.(non-Class lE, tested)

(e)

Struthers Dunn (SD), Model 219BBX239NE (Class lE), Model 219BBXP, 27VDC, (non-Class lE tested)

(f)

Struthers Dunn (SD), Model 219BBX232NE (Class lE), Model 219BXP, 24VAC, (non-Class lE tested)

Insert B For these cases where the non-Class lE version of the relay was tested (due to non-availability of Class lE' test specimens) it was verified that the-relay configuration was identified to the Class lE version.

The only construction differences were that the Class lE versions used higher quality insulation materials.

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..... + electromagnetic interference (EMI) conditior,s.

These tests included conducted and radiated transients (100 to 500 KHz, 300 V peak-to-peak amplitude), and conducted and radiated radio frequency (RF) transients 0.5 to 100 MH:, 5 V peak-to-peak amplitude), and voltage surges consisting of a 2.5 kV peak oscillatory wave at a frequency of 1.5 MH:.

5.

Allen-Bradley 700-200 A12P, Struthers Dunn Tyoe 219, Acastat EGP, and Potter & Brumfield MDR Relays

' e digital isolators, i.e., auxiliary relays used by the HCGS ar -

Agasta f e GP, Model EGP-8001 rep h u W A

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in seH-A Allen-Bradley (AB) Typ el 700-P200A1

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Potter & B

.. ield (B&P) Type MDR, Mo 4134-1 Struthers-Dunn (SD) Models 219XBXP and 219BBXP The relays were tested to detemine the ability of their coils, Class IE side, to maintain continuity and operability when their contacts, non-Class lE side, were subjected to various tests including the MCf voltage / current when applied to the output contacts in the transverse mode. The relays were subjected to a *high potential dielectric test, a surge withstand capability test, a maximum credible voltage test, and a maximum credible short-circuit test.

.T;,3,c w E The tests are described as follows:

High Potential Dielectric Test - Application of a 1500-volt potential for 60 seconds between insulation and ground, between relay coil and contacts, and across normally open relay contacts.

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