ML20091N287

Responds to NRC 840423 Request for Info Re Safety Parameter Display Sys Per Suppl 1 to NUREG-0737.Safety Features,Data Validation,Human Factors & Method of Electrical Isolation Discussed.Description of Foxboro Optical Isolators Encl

ML20091N287
Person / Time
Site:	Hatch
Issue date:	06/07/1984
From:	Gucwa L GEORGIA POWER CO.
To:	Stolz J Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737 NED-84-304, TAC-54169, TAC-54433, TAC-54607, NUDOCS 8406120259
Download: ML20091N287 (14)

Text

.

• ' ..- Georgia Power Company -

333 Piedmont Avenue Atlanta, Georgia 30308 -

Telephone 404 5266526, Maihng Address' Post Offce Box 4545 Atlanta, Georgia 30302 Georgia Power L T. Gucwa the southern eiwinc system Manager Nuclear Eng:neenng

.and Chief Nuclear Engineer NED-84-304 June 7, 1984 c

Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Cannission Washington, D. C. 20555

~

NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HMG NUCLEAR PIANT UNITS 1, 2 RESPONSE 'IO REQUEST POR INFOR4ATION ON SAFETY PARAME'IER DISPIAY SYSTEM Gentlemen:

In response to your letter dated April 23, 1984, Georgia Power Company (GPC) provides herein information related to installation of the Safety Paraneter Display System (SPDS) at Plant Hatch. Your questions are restated, followed by the GPC response.

Question:

1. " Conclusions regarding unreviewed safety questions or changes to Technical Specifications"

Response

No changes to t'echnical specifications are anticipated'. A safety evaluation conducted in accordance with 10 CPR 50.59 concluded that the following modifications associated with the installation of the SPDS systen posed no unreviewed safety questions:

a. - Mdition of:100 meter primary meteorological tower and modification

= of existing 150 foot tower as a backup.

b. Addition ' of . SPDS, Operations Support Center, and Bnergency Operations Facility to the Technical Support Center to . function as 1the Energency Response Facilities -(ERFs).

c. Addition, modification', _ or replacanent of . instrtamentation to provide plant parameters to the SPDS and ERF canputers - (class 'IE

. isolation _is provided where necessary).

k N V:o tg,

GeorgiaPower A Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief

. Operating Reactors Branch No. 4 June _7,1984 Page Two Question:

2. "SPDS implenentation plan, including:

2.1 proposed method of data validation;"

Response: l The cmputer systen checks validity of any parmeter prior to display on l the monitors. Data that is probably valid, but cannot be validated (e.g. a redundant signal is not operational) is displayed differently fra validated signals. Invalid data is not displayed. 'Ihe cmputers perform the following checks to determine validity:

a. a check to see if the operator has temporarily deleted an input signal;

b. a check for process conditions which could invalidate the instrment; and

c. a check of the signals in cmparison to available redundant instrm ents.

Question:

2.2 " description of h man factors progra and results, i.e., SPDS design characteristics that have been incorporated into the design so that displayed information can be readily perceived and cmprehended, and is not misleading to SPDS users;"

o

Response

Hunan factors considerations have been incorporated into the SPDS design through several mechanians including:

a. . Work ' place dimensions and general layout conform to guidelines contained in "Hean Engineering Guide to B:[uipnent Design", 1972 edition by Harold Van Cott and Robert G. Kinkade;

b. Information inputs for the displays were determined by Bechtel Power Corporation to -provide the operator the necessary - process parameters. A list of the inputs was provided to the NRC in a subnittal dated August 31,-1983; and '

mm

. I l .1 ~..

GeorgiaPower A l

Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief L

L Operating Reactors Branch No. 4 L June 7, 1984 l

Page tree 1

2.2 (Cont'd)

c. ~ Display design is based on work by the BNROG Control Room Ctenittee and the results of a dynmic screening progran conducted at a BfR simulator.

A formal htman factors review of the SPDS design will be conducted in conjunction with the Detailed Control Pom Design Review (DCRDR) . Scope of the htsnan factors review includes design, operator training, and an SPDS simulator evaluation. Human factors criteria are derived fra the following sources:

i) NUREG 0835, "Hean Factors Acceptance Criteria for the Safety Paraneter Display Systen";

11) NUREG 0700, " Guidelines for Control Rom Design";

iii) EPRI Report NP-lll8, "Hinnan Factors Methods for Nuclear Control Room Design, Vol. IV"; and iv) EG&G Technical Report SSDC-5610, "Htsnan Engineering Design Considerations for CRT-Generated Displays".

Results of the SPDS htsnan factors review will be provided with the DCRDR

. final report scheduled for subnittal to the NRC in June 1986.

Question:'-

2.3 " proposed method of electrical isolation of the SPDS fra safety systens including:

2.3.a For each type of device used to acceplish electrical isolation at Hatch 1 and 2, describe the specific testing performed to denonstrate that the device is acx:eptable for its applications (s). This description should include elementary diagrans where necessary to indicate the test configuration and how the maximtun credible faults were applied to the devices."

Response

he proposed method of electrical isolation of the SPDS fr a safety systems is by use of optical isolators qualified for Nuclear Class lE safety related service.

%e requested test 'results are provided in Ftaboro doctments 00AAA20 and 700775 -

. Georgia Power d Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 June 7, 1984 Page Four (2.3.a cont'd) 00AAB44. Refer to Paragraph 5.4.2 and Figures 22, 31, 76, and 77 of attachment 1.

Question:

2.3.b " Data to verify that the maximun credible faults applied during the test were the maximum voltage / current to which the device is acceptable for its application (s) . %is description should include elenentary diagrans where necessary to indicate the test configuration and how the maximun credible faults wue applied to the devices."

Response

All inputs fran the isolators to the SPDS are run in raceways dedicated for low level instrunentation circuits. ne maximun possible voltage in those trays is 50 volts, which is considerably less than the 600 volts for which the isolator was tested. We tests at the higher voltage provide a wide margin between the test and actual operating condition.

hus , testing assures that the isolators will perform under the most adverse conditions expected at Plant Hatch. Attachnent 1 provides details on the test configuration used for the test program.

Question:

2.3.c " Data to verify that the maximun credible fault was applied to the output of the device in the transverse mode (between signal and return) and other faults were considw ed (i.e., open and short circuits)."

Response

Paragraphs 6.4.2.1, 2, and 3 of Attachment 1 provide the required data.

Question:

-2.3.d " Definition of the pass / fail acceptance criteria for each type of device."  ;

Response

i .

1

Paragraph 4 of Attachment 1 provides acceptance criteria used by Foxboro I in their test progran.

1 1

70077$

Georgia Powerkh Director of Nuclear Reactor Regulation Attetion

Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 June 7, 1984 Page Five Question:

2.3.e "A cmunitment that the isolation devices emply with the enviromental qualifications (10 CFR 50.49) and the seismic qualifications which were the basis for plant licensing."

Response

%e Foxboro isolators are located in the main control rom which is a mild enviroment area as defined by 10 CER 60.49. Accordingly, no s 1 specific enviromental qualification is required. Paragraph 4 of AttacInent 1 provides information relative to the seismic testing for the isolators.

Question:

2.3.f "A description of the measures taken to protect the safety systems fra electrical interference (i.e., Electrostatic Coupling, EMI, Cmmon Mode and Cross-talk) that may be generated by the SPDS."

Response

Hardware for the SPDS c m puters and monitors meet MIL-S'ID-416A (cmputers) and MIL-S'ID-416 B (monitors) . The standards assure that the sluipnent is suitable for severe battlefield enviroments. % e hardware contains shielding to keep EMI enissions to a minimm as well as assure that the equipnent is imune _ to EMI fra external sources. Hardcopy devise is not a MIL-Spec unit, but Ineets FCC Rules, Part 15 for Class A Computer Bluipnent. A large steel console used to house the equipnent provides additional shielding.

Computer cmununications are by fiber-optic cable which is expected to eliminate potential problems fr m noise, cross-talk, etc.

l Question:

l 2.4' " proposed schedule for full implenentation, including hardware, se e, training, procedures / operator manuals."

Response

Proposed schedule for implanetation was provided on April 15,1983 in our response to Generic Letter 82-33. Full implenentation is scheduled for June, 1986.

700775

i. . ' ,

l ey .

\ .A s

_,T'c GeorgiaPower d <

Director of Nuclear Reactor Regulation ,

L i Attention: Mr. John F. Stolz, Chief

-Operating Reactors Branch No. 4 June 7, 1984 Page Six Question: ,

3. " Description of an additional parmeter selected to serve as a Radioactivity Control safety function monitor during containment isolation conditions." ,

Response

Our position is that the parmeters provided on the SPDS and discust.ed in the August 31, 1983 subnittal are adequate to assess the safety status of the plant. We believe the proposed systen fully meets the raluirenents of NUREG 0737, Supplenent 1. Additionally, the post accident sapling systen (PASS) is provided to saple the containnent air. The PASS is an inline sapling systen with grab saple capability. 'Ihe data is not provided to the SPDS conputer, but will be available to the operator.

Drywell radiation level is available on the SPDS on a pageable display

, which could be selected by the operator when needed. Range of the display is 1 R/hr to 107 R/hr. ,

('

Please contact this office /e any questions or ccimments.

Verytrulyyours, c

g [ g_ sg I L. T. Gucwa w

g

.s xc: H. C. Nix, Jr. /

J. P. O'Reilly (NRC- Region II)

, Senior Resident Inspector

+

t c IMIIS

'C0AAA20 PART 1 ATTACHMENT 1 PAGE 8 REV A FOXBOR0 DOCUMENT Q0AAA20 2&P+SLM Style A Signal Limiter 2AP+SSL Style A Signal Selector 2 AO-IPD-S Style A Intergrator Power Driver (Solid State) 21X+DIO Style D Distribution Modules 2 AC+DYC-L Style A Dynamic Compensator 2AX+ES Style A Blind Set Plug 2 AX+DT Style A Temperature Difference Module

4. ggyCLg11ggs Gling_1E_gualification - Eerformance_griteria With the exception of the 2AO-L2C-R Contact Output Isclator, which chattered during seismic tests, all modules performed their Class 1E f unction during and after seismic tests and were within the performance acceptance criteria noted in Test Procedure

(')

00AAA04 Part 1, and are theref ore qualified to the Test Response Spectra (TR S) levels achieved in testing. I Both the style A and ECEP 10273 version of the 2 AO-L2C-R Contact Output Isolators had output contacts which chattered during tests (i.e., had openings or closures of greater than 100 us) . One output (two were monitored) of the Style A version chattered during only one SSE in the lef t-to-right plane. During all other SSE's and OBE's no chattering occurred. ,

Both monitored outputs of the ECEP version chattered during the right-to-lef t and front-to-back planes of the SSE test. Neither output chattered during the OBE test levels. Therefore, without" modifications both 2AO-L2C-H Contact Output Isolators ar.e _onl.y qualified to the OBE level and not the SSE level.

At the time of this report Foxboro is in the process of investigating other Relays which, hopef ully, would perform satisf actorily at the SSE level. ., l The output shif ts on all other modules except two, during all OBE  !

and SSE tests, were less than 0.25%. The two exceptions were as follows: /

1. The 2AX+ TIM timer's output No. 2 (1 to 30 sec timer) shif ted as much as 0.5% during the SSE tests. However, this shift was well within the 120% accuracy specifications.

1

2. Output A of 2AP+1LM-AS Alarm fired during the SSE in tne lef t-to-right plane. This alarm was tested as a high alarm i l with the set point at 51% and the input at 50%. The firing was caused by the set point- potentiometer shif ting -2.0%, crossing the input, and causing the' output to change state. During th e other three SSE's the maximum shift observed on this potentiometer was -0.3%. Also, it should be noted that three l other set point potentiometers (two in the 2AP+ ALM-AR Alars a nd i the remaining set point potentiome ters in the 2AP+ ALM- AS Alarm)

vere tested, none of which had shifts greater than 0.1% during any OBE'or SSE~ test so the potentiometer that shifted was nontypical. Measurements were made of the torque required to chaage the setting of the potentiometer which had shif ted af ter

QOAAA20 PAFT 1 PAGE 9 R EV A seismic tests were completed. It was found to require a torque of ' O.05 inch-ounces compared to the other three potentiometers which had minimum torque requirements of 0.15 inch-ounces.

Therefore, a specification of 0.20 inch-ounces minimum torgue has' been established for all potentiometers used in nuclear-related 2AX+ ALM alara cards.

It is reiterated that the -2.0% shif t of the nontypical unit was within target acceptance criteria. Powever, with the addition of the above specification a maximum set pcint shif t of 1.0% would be expected.

giggg_jI_ggalifig3 tion _ggig3 i c Criteria A comparison of 1% damped TRS's, plotted at one-third octave intervals, to target Required Response Spectra (RR S 's) for generic class 1E qualification of rack-nounted modules is presented in Figures 41 thru 72 f or nests 1,2,3, and 4. Please refer also to Graphs 79, 80, 81, and 82 which are composite plots of all 1/3 octave TRS Data Points for Nests 1,2,3,4 compared to the target RRS's. A review of these plots indicates that 954 of the one-third octave data points exceeded the target FRS values.

A majority of the remaining points are attributed to test table performance problems. A significant number f all in the 1 to 2.5 hertz frequency range as a result of test table velocity limitations. Most of the points also occurred in the vertical test response spectra. Since amplification factors ottained in the vertical response are much lower than those obtained in the horizontal response, the points of marginal undertesting in the vertical axis are not considered to be significant relative to module perf ormance obtained in testing.

Other data points are considered to have resulted frcs inconsistencies in test table performance related to the high mass and center of gravity of the fully-loaded N-2ES rack.

In view of the extensive similarity of design and- function among C, the modules tested and the degree of success achieved in enveloping the target generic RRS's for qualification of rack-acunted modules, Foxboro considers the seismic qualification criteria'of Figures 1A, 1B, 2 A, and 2E to have been met.

Additional 11, 2.5%, and - 55 damped T3S's applicable tc nests 1,2,3, and 4 andlto the Multi-nest Power Supply at both OBE and SSE test. levels are included in Section 8 cf this report.

The SSE ficor-level response spectra to which the SPEC 200 nodules of this report have been qualified _in_gpegific N-211 EREl_19&diDS_E9BliSEIAti2Rg vill be addressed in an appendix to this report.

to. l 00AAA20 PART 1 PAGE 25 REV A t

1 i

5.3.9 2A E11N T-!_E111 1_ A_111aER_1991_Inigggaigg I

a. 5 OBE Tests l

_________Outant_Ehiftt_%___ ___ f Plane of During rest After Test Yihra119n ___52% ___ _01_ 1025

<0.4 <0.1 <0.1 Front-to-Back Back-to-Front <0.4 <0.1 <0.1 Left-to-Right <0.4 <0.1 <0.1 Bight-to-Left <0.4 <0.1 <0.1

b. Eg3_T2stE (I

_________921Ent_Shiftt_5 Plane of During Test After Test 0% 100%

lihgatign ___10%

P r ont-to-Ba ck <0.4 <0.1 <0.1 B ack-t o-Fr ont <0.4 <0.1 <0.1 Le f t-to-Bigh t <0.4 <0.1 <0.1 Right-to-Left <0.4 <0.1 <0.1 5.4 Nest Egz_1 5.4.1 2AliDEP_ Hitl e D pigtEih1119E_39dule This instrument ls a passive device and therefore was not operational during tests. It functioned properly after all tests.

5.4.2 2AO-VAI Isolatigg_Tggt

1. 2A2-VAI oulpyi Termin als Gggugsej Neither channel of the 2AI-I2V Current-to-Voltage Converter which fed the 2 AO-V AI V oltage-to-Current converter shif ten more C' than'0.5% when one channel of the 2AO-VAI's output was grounded. Also both channels of the 2AO-V AI functioned properly fter the test was completed. Pefer to Figure 76 for

' oscillograph recording of 2 AI-I2V outputs.

2. 600 V ag_betw egn_gytant a gg_ggpupg2 Both the' 2AO-V AI and 2 AO-Y2I remained operational during this

. test. There was some ac feedthrough to the 2AI-I2V. Refer to Figure 77. f or recording s of outputs.

3. ' Agg_1_a g_Actass_th e_Qginat_Lgajg The application of 600 Y ac across the output terminals of Section A of '210-VAI S/N -3671610 produced the following damage to the unit:

n '.

-QOAAA20 PART 1 PAGE 26 REV A

1. Circuit foil from the + output lead connection to J9 opened.

2. Circuit foil from the - output lead connection to J14 )

opened.

3. Resistor R32 (402,13%, 6 W) opened. i

4. Capacitor C17 (6.8 uF tantalum) opened.

5. Capacitor C11 (4.0 uF polycarbonate) shorted.

6. Dio$es CR19, 20, 21, and 22 (Type 1N 4 4 47) opened. .

Reference:

Schematic No. 13102FY; Drawing No. 10201NZ No damage occurred to Section B or to the 2AI-I2V Voltage-to-Current Converter due to the application of the test voltage to Section A. Pefer to Figure 7 8 for the 2 AI-I2V output recordings.

5. 4. 3 2Axippg_glyle_C_pistriba tion Hodule The 2AX+DSC was used to connect a 2AC+ A5 Controller and 250PM Display Station during all tests. The controller and display station operated properly bef ore, during and af ter all OBE and SSE te st s.

5. u. 4 2 A B PE R1Hg2_Etyle _Q_3 gl11- peg 1_ P ow e r_ S uppl y_wi th Battery Eaghgp

a. ggE_Issig

_____________QutE21_Ehift t_%

Plane of ___Dprig g_Te gt __ __ __

After_Tegt _

lihElt19D is9_I 219_1 ag_1 +de V -dc V ac V Front-to-Back <0.75 <0.75 <0.8 <0.1 <0.1 <0.1 Ba c k-t o-P r ont <0.75 <0.75 <0.9 <0.1 <0.1 <0.1 Left-to-Right <0.75 <0.75 <0.8 < 0.1 <0.1 <0.1 ,

Right-to-Left <0.75 <0.75 <o.8 <0.1 <0.1 <0.1

b. j$E_Iggi

____________9Etent_ shifts _%

Plane of ___During_Iggt After_ Test- _

lihE1119D igg _1 ;de V a V +de V -dc V ac V Front-to-Back <0.75 <0.75 <0.8 <0.1 <0.1 <0.1 Back-tc-Front <0.75 <0.75 <0.8 <0.1 <0.1 <0.1 Left-to-Right <0.75 <0.75 <0 . 8 <0.1. <0.1 <0.1 Right-to-Left <0.75 <0.75 <o.8 <0.1 <0.1 <0.1

c. The 120 Y ac power to the 2ARPS-A6 Power Supply was removed during one OBE and one SSE to ensure proper i switching to battery backup during seismic tests. No problems were encountered.

( O 9

00AAA20 PART 1 PAGE 59 REV A Figure 22 Seismic Test Setup 2AO-VAI Voltage-to-Current Converter 2AX+P W

INPUT A 2500h, (R Voltage 2AO-VAI f Source --*F, yo .

DVM INPUT B 2500g' (R 12&L G9BO LAS.Q21 Input at 5 1 det output recorders calibrated for full scale traverse of 12 mA tSt

'e a QOAAA20 PART 1 PAGE 68 REV A l

Figure 31 Seisaic Test Setup 2AO-VAI ECEP 9206 Voltage-to-Current Converter

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Three tests are to be performed: 1) Ground 2) both outputs of Apply 600 Y ac between Channel A f or 10 seconds during 1 SSE.

both output leads tied together and ground for 10 seconds during ancther SSE. 3) apply 600 Y ac across the output leads during a third SSE f er 10 seconds; current source input at 12 mA, recorders calitrated for full scale traverse of 5 Y de 15%.

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