Text

Status of Compliance W/Rev 2 to Reg Guide 1.97
	ML20215H773
Person / Time
Site:	Millstone
Issue date:	06/30/1987
From:	; NORTHEAST NUCLEAR ENERGY CO.
To:	;
Shared Package
ML20215H745	List: ML20215H741; ML20215H773;
References
	RTR-REGGD-01.097, RTR-REGGD-1.097 A02959, A04770, A2959, A4770, NUDOCS 8706240209
	Download: ML20215H773 (26)
	v • d • e

-_ - __-____ _ - _ _ _

a Docket No. 50-336 J

A04770

~

A02959 Attachment No.1

.g.

Millstone Nuclear Power Station, Unit No. 2 Status of Compliance with Revision 2 to Regulatory Guide 1.97 l.

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i June 1987 8706240209 870615~

DR ADOCK 05000336 PDR

_ _ - - __ _ - _______ - - - _-__-__-__. __ _-__ - - __- -_-_______ _________-_=_ __- _________ _________-____-_- -_____-__--_ -_______-__- ______

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This attachment presents a table summarizing the status of compliance of' Millstone Unit.No. 2 with Regulatory Guide i.97, Revision 2.

The following is an' explanation of the terminology used in the various columns.

t

~ VARIABLE -' A single asterisk ("*") af ter a variable number indicates 'that the variable is-monitored but not considered part of the post-accident monitoring system.

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A double asterisk ("**") af ter a variable number indicates that the variable is not monitored and is not considered part of the post-accident monitoring system.

INSTRUMENT RANGE - Where the NRC and Millstone Unit No. 2 instrument ranges are not directly comparable due to unit differences, the Milistone Unit

. No. 2 ranges meet or exceed the NRC ranges unless otherwise noted.

EQ. (ENVIRONMENTAL QUALIFICATION) - A "yes" entry means that the j

.instruinent_ is or will be qualified in accordance with the qualification -

l requirements of 10CFR50A9.

i

' SEISMIC QUALIFICATION - A "yes" entry means that the instrument is or wili J

be' qualified to present licensing commitments.

QA (QUALITY ASSURANCE) - A "yes" entry means that the -instrument is considered Cat.IE by NNECO. Maintenance and spare parts procurement are in accordance with NNECO's QA program.

i SCHEDULE. - If this column is lef t blank, Northeast Nuclear Energy Company considers the existing instrument to be adequate for the intent of the regulatory guide. A " year" entry means the refueling outage of that year when replacement is scheduled to be completed, j

POWER SUPPLY - A "REL" entry means reliable. This power supply is backed up by the diesel. "iE"- power at Millstone Unit No. 2 is the vital ac which is a non-interruptible power supply.

I LOCATION OF DISPLAY:

I CONTROL ROOM, TSC AND EOF - An "1" entry means it has continuous indication, and "R" is continuous recording unless otherwise noted.

"R*"

indicates the provision of the guide which could either be continuous recording or stored in computer memory and displayed on demand. The "ERIS" entry, l

which stands for. the Emergency Response Information System, should be disregarded at this. time.

We are continuing our evaluation to determine whether additional information needs exist in the TSC and EOF.

1 l

l

,i-(..

l LOCATION OF SENSOR:

CNMT - Containment A.B.'- Auxiliary Building T.B.'- Turbine Building '

For Category 2 variables,.the location of sensors is further classified as harsh or non-harsh environments.

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1 i

I NOTES:

l Note 1: The present 2,050 ppm range is sufficient to monitor beyond the Technical Specification limit of 1,720 ppm. In cases where higher range is required, the Post Accident Sampling System (PASS) will be utilized.

Note 2: Based on the safety analysis of the plant, the existing range of 0-6000F is sufficient to monitor cold leg fluid temperature conditions following l

all design basis accident scenarios.

Note 3: Since 2120F is the saturation terr.perature at atmospheric pressure, the 1500F lower range provides sufficient margin to monitor the approach to saturation in a cold shutdown situation in the event of a loss of I

shutdown cooling.

Note 4: The full range is covered by several instruments with ranges of 0-1,600 psig, 1,500-2,500 psig and 0-3,000 psig.

The 1,500-2,500-psig instruments are Cat. IE instruments. The 0-1,600 range instruments l

were upgraded during the 1983 outage. The 0-3,000-psig instrument is a i

i non-Cat. IE single-channel instrument powered from a reliable nonvital power supply with continuous recording. NNECO considers the upper

- range of 3000 psig adequate for all design basis events.

i Note 5: Deleted.

Note 6: The proposed range has been justified in NNECO's reply, dated March 11,1983 to D. G. Eisenhut letter to all licensees of operating j

r 1

~ Westinghouse and CE PWRs (Generic Letter 82-28) dated December 10, 1982. Also, Revision'3 to Regulatory Guide 1.97 only requests a range from the bottom of the hot leg to the top of the vessel.

Note 7: Deleted.

Note 8:

No existing in-line monitor. The Post Accident Sampling System (PASS) will be utilized. - The PASS was recently installed in accordance-with NUREG-0737, item II.B.3.

The required range of activity can be analyzed.

1 Note 9:

This parameter has been deleted in Regulatory Guide 1.97, Rev. 3.

Note 10: The tank design pressure is 250 psig.

Note 11: The Acoustic Valve Monitoring Sys.em (AVMS) was upgraded during the 1983 refueling outage.

Note 12: The pressurizer heaters are rionitored by breaker status indicating lights.

Note 13: This is a horizontal c' ylindrical tank with a 60-inch O.D. The instrument measures 40 inches of the center of the tank.

.l Note 14: The range of 0-3000F is sufficient to monitor normal as well as design l

basis accident scenarios.

i I

Note 15: There are no instrument taps in the S/G to allow direct wide-range level measurement.

i Note 16: Steam generator pressure is recorded by Category 2 instruments. See variable D-17.

Note 17: There is no existing instrument to indicate the safety relief valve position. New instruments will be installed.

a Note 18: The condensate storage tank level instrumentation consists of an electronic level instrument loop with alarm and continuous indication in the contro! room. In addition, a pneumatic level controller with local indication and high and low alarms is also available in the control room. The electronic loop has been upgraded while the pneumatic loop will be kept as is because of the inherent reliability of pneumatic instruments.

These instruments are located in a ncn-harsh environment.

Note 19: There are several RTDs that go to a selector switch in the control room. A single indicator is used to indicate the selected RTD. The maximum predicted containment temperature is less than 3000F.

s Note 20: This parameter is an input to the plant process computer, and can be recorded on demand.

Note 21: Deleted.

IU i

y

j

. Note 22: The status of the diesels are indicated by voltmeters, ammeters and '

power meters. The status of the starting air for the diesels is alarmed at the control room. _ Tlie emergency bus' voltages are continuously _-

ilndicated ~at the control room. All sensors are located Lin a mild q

U environment.

Note 23: The area radiation monitors are _ located 'throughout the radiological control areas of the - plant. However, most of them have antupper 1

range of 104 to.106 mr/hr.' The function of the fixed area ~ mon (tor is Lj m

~!

to. warn of changing or unusually high radiological conditions. This can.

c i

' be accomplished with the existing instruments.. Personnel access to.

]

areas ' under accident conditions would-be : allowed only; with.

appropriate portable survey instruments. Also,' Rev. 3 of Regulatory GUlde '1.97 classifies this parameter as Cat. 3.-

Note 24: The previous method of determining noble gas release was by sending' an individual under the main steam line with portable instruments.- To

. meet the provisions of the regulatory guide, NNECO has installed l Area Radiation Monitors at the east steam line and -the west steam lins.

These monitors indicate and record in the control room. The -flow' is calculated using steam generator pressure and valve specifications and.

meets the Instrument range specified in the guide.

Note 25: The stack monitors are equipped with Particulate and lodine filters which are utilized for laboratory analysis.

The required range of 1

concentrations will be met.

1 LJ I

i l

t i

1

)

a s,

y Note 26: The plant is equipped t.with portable instruments which are capable of meeting all the provisions of the guide.

' Note 27: There is only one wide range temperature instrenent in each of the t

hot legs and cold legs.

m

)

i Note 28: The.lowSr ' : range of 10. psia is covered bp'-the wide. range

>Y instrumentation.

t l

d

, L, sNote 29: De ete.

l'

' Note 30: Design verification' indicates that this level range can measure up tE '

565,000' gallons.

This is acceptable because the maxinium post-accide'nt containment. water volume will not exceed ' approx}mately

~ 563,800 gallons. Details are provided in the W. G. Counsil letter to R.

A. Clark, dated,Jarch 8,1933.

t Note 31: The analyzers are designed for operation under a positive containment pressure up to -10 psig.' The Millstone Unit No. 2 containment will not i

see a negative pressure under any FSAR analyzed accident conditions.

This pressure range is presently being addressed under NUREG-0737, item II.F.1, Attachment 6.

(See W. G. Couosil letter to 3. R. Miller, dated March 27, 1984).

Note 32: The pressure and level indications for the safety injection tanks are f) 8 important in verifying the operability of the system during normal operations. However, their importance is diminished during and af ter an accident, for the following reasons:

J b

~

l l

4 ;. _;

(M l

p

' a; They provide no automatic function.

I!

b. No operator actions are based on their indication.

c. The system is passive and functions early in an accident (LOCA).

8 Note 33: The hydrogen analyzers were modifec' in response to NUREG-0737, f

1 Item II.F.1, Attachment 6.

The sensitive electronic parts of the 1

l system were moved from a potentially harsh environment to the i

Control room.

T

(-

' f <

Note 34: The PASS does not have the capability to analyze for dissolved 0 -

2 6p The NRC Staff concluded our-PASS was acceptable in the Safety i

Evaluation on NUREG-0737 Iteb II.B.3, transmitted in 3.R. Miller's T,q.

letter to W.G. Counsil, dated June 14,1984.

Note 35: Motor ammeter readings in the control room are utilized to back up the flow indication. The sensors for the ammeters are located in mild environments.

in addition, failuiu of the flow indication does not

.1 jeopardize the operability ofqhe system it is monitoring.

Note 36: Charging header pressure can be used to back up the charging flow indication.

l t

i a

Note 37: Pressurizer level or differential pressure across the letdown filter can i

be utilized to back up the letdown flow indication.

~

i i

L a

- a

r Note 38: RHR heat exchanger outlet temperature can be verified by trending reactor coolant temperature.

Note 39: This information is displayed in the Millstone Unit No. I control room.

Note 40: The pressurizer level. instruments were upgraded during the 1985 refueling outage to meet EEQ requirements. The instruments are part of the cabinets which were procured mainly for the feedwater control system. These cabinets are powered from an instrument power supply I

that is highly reliable but not category 1E. Although this power source is not classified as category lE, the diesel generators provide backup power. The only difference between a category lE power supply and this instrument power supply is that the category lE supply is backed by the station batteries via the inverters which ensures that there is no momentary power interruption during transfers from " normal" to

" emergency" power and vice versa. The design of the instrument power supply will result in a momentary interruption during transfers, however, the pressurizer level instruments are designed to tolerate these momentary interruptions.

Based on the above, it is concluded that the pressurizer level instru-mentation, as modified, is adequate for post-accident monitoring functions.

i Note 41: The key variable required to assess the condition of the containment is containment pressure. Containment temperature is utilized only in a j

8 1.

diagnostic capacity. Based on the above, it is ' concluded that this parameter is category 3 which is a "high quality, off-the-shelf" instrument powered from a highly reliable power supply.

Note 42: CCW to ESF systems is provided by the RBCCW system. The RBCCW outlet temperature is the CCW temperature to ESF system. These instruments have no safety function and their failure does not jeopar-dize the operability of the RBCCW system. Based on this, the existing instruments are judged to be adequate.

Note 43: The narrow range sump level instruments are utilized during normal operation to indicate level and initiate an alarm for the operator to manually start the sump pumps. During an accident, the sumps would be filled and the operators will not start the sump pumps, to avoid

)

transferring contaminated water outside the containment..

i

~

i To monitor containment water level following an accident, the wide i

1 range containment level instruments are utilized.

l l

Note 44: Upon reevaluation, it was determined that seven (7) containment

solation valves located outside containment need to have their position indication upgraded to be fully qualified under Regulatory Guide 1.97. Accordingly, the following containment isolation valves will have their position Indication upgraded during the refueling outage scheduled for January - March,1988 to ensure that these val <es communicate proper position indication to the control room during post-accident conditions.

o 2CH-198 - RCS Bleed-off o 2 AC-47,12,15 - Containment Atmosphere Sampling

-l o 2EB-92,99 - Containment H2 Purge j

i o 2 SSP-16.2 - Normal Containment Sump Discharge l

I j

l l

1 l

l l

i l

Docket No. 50-336 A0I770 4

A02959 Attachment No. 2 l

Millstone Nuclear Power Station, Unit No. 2 Control Room Design Review Human Engineering Discrepancies 1

l June 1987

\\

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.o'.,

a, '.,

MP2 HUMAN ENGINEERING DISCREPANCY HED No.

TA-032 TITLE:

Information Requirements PRIORITY:

1 1

j COMMENT:

Off-Scale' Meters

'i Reviewer-Date Ref.

Source i

CT 1-14-86 EOP2525(N-3.16)

TA IDENTIFICATION:

Panel:

C05 Component Name:

SG Level ID OR-NO.:

None

)

DESCRIPTION:

j The procedure caution note has level going below 0%

after trip but no indication is provided until it returns to an indicating range. All SG Lvl Indicators are. Narrow Range. No Wide Range available.

L POSSIBLE SOLUTIONS:

Provide Wide Range Level Instruments l

1 RESOLUTION:

(Code A

-)

Correct / Enhance I

Add WR level instruments for both SG's.

+

See Enhancement Design for location.

See memo MP2-CRDR-86-031.

.h A

7' #/[6 I'

Approved Signature:

Date:

f / / Additional page(s) attached

i_____.________________.__._________.__.____.______________._____________.____.___________.__.________________

L lt i

~ ;l SQ MP2' 5

HHUMhN ENGINEERING' DISCREPANCY'

~

HED No.-

TA-009 g

TITLE:

. Procedural-Instructions-PRIORITY:

1 i

COMMENT:

Procedure indicates to take an action-Reviewer Date Ref.-

Source

'~

CT l-14-86' EOP2525(C-3.3.a)

TA IDENTIFICATION:

Panel:

C03 Component Names-PZR Heaters f

ID OR NO.:

PROP & BACK-UP HTRS DESCRIPTION-The proceduref ndicates to manually control the PZR HTRS i

L

.to return the Pres to 2225-2300 psia.

The question raised-

.was if at first the operator needs to evaluate this need due to systemLdynamics and the proportional heaters. Also the' Control is-a Demand Device. His feedback is the PZR PRES

{l output' signal.on:the controller.

POSSIBLE SOLUTIONS:

RESCLUTION:

(Code A

)

Correction / Procedure Revise procedure to " evaluate" the use of the HTRS.

HTRS - Add meters (2) to each bank of proportional heaters for indication of' operability of the controller. The lights only' indicate the C/B (not the con' troller) is on/off.

See memo MP2-CRDR-86-031.

.b l} if I i Date:

8 Approved Signature:

- 'f

/

/ / Additional page(s) attached L

h-

'y L

'

ML20215H773

Text

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