ML18030A896

Forwards Revised Response to Reg Guide 1.97.Range for RCS Pressure Indication Changed from 0-1,500 Psig to 0-1,200 Psig to Increase Accuracy of Instruments

ML18030A896
Person / Time
Site:	Browns Ferry
Issue date:	11/20/1985
From:	Hufham J TENNESSEE VALLEY AUTHORITY
To:	Vassallo D Office of Nuclear Reactor Regulation
References
RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 8511260230
Download: ML18030A896 (17)

Text

REGULATORY'ORMATION>>DISTRIBUTION 'SY M (RIDS)

.L ACCESSION'BR; S511260230.

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'Authori:ty REC IP ~ NAMEI RECIPIENT'FFILXAT'ION VASSALLO<D ~ BE Operating, Reactors Branch; 2;

SUBJECT:

Forwards reyise'd response'o Reg. Guide 1,97 ~ Rangel for>>>>RCS'ressur el indicatioq changed from.-O. 1~500>>psig to 0.-1~200; psig, to incr ease>> accuracy

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'ENNESSEE VALLEYAUTHORITY CHATTANOOGA, TENNESSEE 37401 5N 157B Lookout Place November 20, 1985 Director of Nuclear Reactor Regulation Attention:

Mr. Domenic B. Vassallo, Chief Operating Reactor Branch No.

2 Divisi.on of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

205S5

Dear Mr. Vassallo:

In the Matter of the Tennessee Valley Authority Docket Nos.

50-2S9 50-260 50-296 The enclosed information updates our response to Regulatory Gui.de 1.97 provided in our letter to you dated April 30, 1984 and supplemented by additional information provided by our letter dated May 7, 1985.

The range for the Reactor Coolant System (RCS) pressure indication has been changed from 0-1500 psig to 0-1200 psig.

This revt,sion was needed to increase the accuracy of instruments.

The following pages of our April 30, 1984 letter are replaced in their entirety by this submittal:

Table 1 Pages 1 and 2 Provide correct RCS pressure indi.cator range Attachment A Pages 9, 17, and 22 Provide correct RCS pressure indicator range Attachment B Issue 3 Add Issue 3B to provide justification for RCS pressure indicator range other than as specified by Regulatory Guide 1.97.

8>> ia602SO 8>> <~00>59 PDR ADOCK 0500 F

PDR An Equal Opportunity Empioyer

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Director of Nuclear Reactor Regulation November 20, 1985 If you need additional information, please get in touch with us through the Browns Ferry Project Manager.

Very truly yours, TENNESSEE VALLEY AUTHORITY W.

HU h i ensing nd nager i k Protection E,Subscribed an worn to before me o thighday f

. 985.

Notary Public My Commission ExyisesR 24 SF Enclosures cc (Enclosures):

Mr. R. J, Clark U.S. Nuclear Regulatory Commission Browns Ferry Project Manager 7920 Norfolk Avenue

Bethesda, Maryland 20814 U.S. Nuclear Regulatory Commission Region II ATTN:

Dr. J. Nelson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323

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ENCLOSURE REVISED RESPONSE TO REGULATORY GUIDE 1 '7 FOR BROGANS FERRY NUCLEAR PLANT UNITS 1, 2, and 3

TABLE 1

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PQ 1.97 Type-Cal, 1,97 I.ar.re TVA Type-Cat TVA Parge Reaarka Al Ccrta 1 sr Rant Bydrc rare Cone ectr a% I rare 0- to 30-percent A-l 0

a o 2n paarceee

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0- to 100-percent See Cll A2 lI'13 Dryrrcll Pressure DryRr ll Air Temperature B-l D<<2 x des'"r 40oF to "40oF A-1 0 psia to 300 psig 0 to 400oF gee BT, B9, C8,~,

D4, and Issue 5~.

lee D7 Bl B?

tieutr on Flux Control Bod Position B-3 10 percent to 100-percent Full in or not f'ull in B-3 B-3 10 6.percent to 125 per cent Full in or not f'ull in See Issue 1

"r B3 BCS Soluble Boron Conct.

B4 Coolant Level in Reactor B-3 B-l 0 to 1000 ppm Bottom of core sup-port plate to lesser of top of vessel or center line of main steam line.

B-3 B-1 Implement as E12 1/3 core height to 228 inches abov'e TAF See Issue 2

B5 B7 B8 BlfB Core Temperature BCS Pressure Dryrrell Pressure Drykrell Sump Level Primary Containmcnt Pressure tiot required at this time 0 to 1500 psig 0 to design Top to Bottom

-5 psig to design B-1 A-1

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B-3 A-1 0 to 1200 psig 0 psia to 300 psig 0 to 150 gpm 0 psia to 300 psig See C4 and Issue 3

see A2, B9, c8 I c 1 0 I D4, and Issue 5

See C6 and Issue 4

see A2, B7, c8, clOI

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D4 and Issue 5

TABLE 1 (conttd)

CR VarI able PCIV Position Pad.

Core. or Level in Primary coolant 07 ypea I at Le

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~ il Range Closed Hot Closed 1/2 TS to 100 TS B-l Closed - Rot Closed Implement as E'l2 TV Tomcat Tea ReeIe asserts See Issue 6

See Issue 7

Aralysis of Primary Coolant C

3 10 ilCi/m'0 Ci/ml Implement as E12 1C3 BUR C re Temperature PCS Ptessurc Rot required at this time C-1 0 to 1500 psig 0 to 1200 psig See B6, C9, and Issue 3

C5 Primary Cont. Area Radiation C6

< Drywall Dr ain Sump Level Suppression Pool Mater Level C 3 C-1 C-1 1 R/hr to 105 R/hr Top to Bottom Bottom of'CCS suction line to 5 ft.

above normal uater level C-3 B-3 C-1 1 to 107 R/hr 0 to 150 gpu 0 to 200 inches (1)

Seo El See B8 and issue 4

I Soe D5 CB Drywoll Pressure RCS Pressure C10 Primary Containmcnt Pressure Cl:

Cort. ilydrogen Concentration (1TMo

." t from bottom of'rus to five feet a"CVe rcrmel RRater lCVOie C-1 C-l C-l C-1 0 to design 0 to 1500 psig

-5 to 3x design 0 to 30 vol-porcent A-1 A-1 A-1 0 psia to 300 psig 0 to 1200psig 0 psia to 300 psig 0- to 20-'percent,,

0- to 100-percent

. 'See A2, DNR and Soe B6, 1

Issue 3

Seo A2, D4 I and Seo Al B7; B9, C10, Issue 5

CCR and B7, B9, C8R Issue 5

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IDENTIFIER:

VARIABLE:

TYPE:

CATEGORY'6 RCS Pressure

(~)

B, C

~'2 INSTRUiSNT NVMBER:

INSTRUMENT RANGE:

REDlJNDANCY:

POMER SUPPLY:

LOCATfON OF DISPLAY:

SCHEDULE:

REHARKS:

PI-3-74A and PI-3-748 (~)

0 to 1200 psig 2 separate channels Class lE Control Room In accordance with integrated schedule P~ur ose:

Core cooling, maintain reactor coolant system integrity, detection of potential for or actual breach of reactor pressure boundary.

(~)

See also C4 and C9.

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See Issues 3A and'B

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~ a 17 IDENTIFIER:

VARIABLE:

. TYPE:

CATEGORY:

INSTRUNENT NUHBER:

INSTRUNENT RANGE:

REDUNDANCY:

POMER SUPPLY:

LOCATION OF DISPLAY:

SCHEDULE:

REHARKS'4 RCS Pressure

(~)

B, C

PI-3-74A and PI-3-748 0 to 1200 psig 2 separate channels Class 1E Control Room In accordance with integrated schedule

~pur oae:

Detection of potential for or actual breach of the reactor coolant pressure

boundary, accomplishment of mitigation and long term surveillance.

(~)

See also B6, C9 and Issues'3A and 3B

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a 22 IDENTIFIER:

VARIABLE:

TYPE:

CATEGORY:

C9 RCS Pressure

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INSTRtMHT NUMBER:

PI-3-74A and PI-3-74B INSTRUMENT RANGE:

REDUNDANCY:

POVER SUPPLY:

0 to 1200lpsig 2 separate channels Class 1E LOCATION OF DISPLAY:

Control Room SCHEDULE:

REMARKS:

In accordance with integrated schedule P~nr oae:

Detection of a potential for breach in the primary containment and accomplishment of mitigation.

(~)

See also B6, C4 and Issues 3$ and 3B

Issue 3A and 3B Variable B6 RCS Pressure Regulatory Guide 1.97 states that recording of instrumentation read-ouQ information will be providbd for at least one redundant channel.

Contrary to that, no recorder from a qualified instrument channel will be provided for RCS pressure.

Reactor pressure is a Category 1 Type B variable.

Two independent qualified channels for indication are provided in the control room.

This parameter will not,

however, have a recording device from a qualified channel in the control room.

This information is not essential for the operator's direct and immediate trend or transient information. It does,

however,

.have a pressure r ecorder displayed in the control room that gets its signal from a nonqualified instr ument loop that the operators use during normal operation.

Reactor pressure will also be included in the database for the Safety Parameter Display System (SPDS).

Two independent control room indicators from a qualified instrument loop for reactor pressure is sufficient for operator's use during accident conditions.

The reactor pressure will also be input to the SPDS.

ssue e

0 Regulatory Guide 1.97 states that the range of the RCS pressure indication will be 15 psia to 1500 psig.

Contrary to that, the range of the instruments to be provided will be 0 to 1200 psig.

The 0 to 1200 psig range provided in the category 1

RCS pressure indication covers the full range of pressures for which operator actions are initiated during accident conditions.

The only postulated need for monitoring pressure greater than 1200 psig would be to document peak pressure during a reactor transient.

This would require recording capability and would be handled by the 0 to 1500 psig range recorder described in issue 3A.

Based on the discussion

above, the 0 to 1200 psig category 1 instruments provided to monitor RCS pressure are adequate for postaccident monitoring.

1.

TVA letter from L. M. Mills to H.

R. Denton, NRC, dated April 30, 1984 (A27 840430 007) 2.

TVA letter from J.

A. Domer to D. B. Vassallo, NRC, dated May 7, 1985 (L44 850507 800)

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