ML20153D677

Forwards Attachment II to Util 851031 Response to Request for Addl Info Re Reg Guide 1.97,inadvertently Omitted from Original Submittal

ML20153D677
Person / Time
Site:	Rancho Seco
Issue date:	02/11/1986
From:	Reinaldo Rodriguez SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Thompson H Office of Nuclear Reactor Regulation
References
RTR-REGGD-01.097, RTR-REGGD-1.097 RJR-85-579, TAC-51126, NUDOCS 8602240213
Download: ML20153D677 (16)

Text

-

l

$suu.

SACRAMENTO MUNICIPAL UTluTY DISTRICT O 6201 S Street. P.O. Box 15830, Sacramento CA 95052-1830.(916) 452-3211 RJR-85-579 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA February 11, 1986 DIRECTOR OF NUCLEAR REACTOR REGULATION ATIN HUGH L THOMPSON JR t

U S NUCLEAR REGULATORY COMMISSION WASHINGTON DC 20555 DOCKET 50-312 RANCHO SECO NUCLEAR GENERATING STATION UNIT NO. 1 REGULATORY GUIDE 1.97 REQUEST FOR ADDITIONAL INFORMATION The District, in its October 31, 1985 submittal, inadvertantly omitted Attachment II, which is herein enclosed.

In the interests of continuity, the entire package is being resubmitted.

If we can provide any additional information, please advise.

/

\\g R. J. R00 IGUEZ ASSISTANT GENERA

ANAGER, NUCLEAR Enclosures 8

8602240213 860211 PDR ADOCK 05000312 gI F

PDR

~. -a ll.li

$SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT C 6201 S street. P.O. Box 15830. sacramento.CA 95813:1916) 452 321 RJR 85-521

' AN ELECTRIC SYSTEM SERVING THE HEART OF CAllFORNIA-

'0ctober 31, 1985 e

DIRECTOR OF NUCLEAR REACTOR REGULATION ATTENTION HUGH L THOMPSON JR DIRECTOR DIVISION OF LICENSING

-U S NUCLEAR REGULATORY COMMISSION WASHINGTON D C 20555 4

DOCXET 50-312 RANCHO SECO NUCLEAR GENERATING STATION UNIT NO 1 REGULATORY GUIDE 1.97 REQUEST FOR ADDITIONAL INFORMATION The District is enclosing in Attachment I, its response to the NRC's request for additional information concerning confonnance to Reg. Guide 1.97. The NRC sent this request based on an interim report prepared by its contractor, INEL. who reviewed the District's various Reg. Guide 1.97..

submittals. The District submitted these reports on September 14, 1983, July 13, 1984, September 14, 1984, and July 9, '1985. The last two reports also contain implementation schedules. The District used its living Schedule process to schedule the Reg. Guide 1.97 modifications.-

To facilitate the review of the infonnation in Attachment I, the District

~

has included in Attachment II, revisions to its September 14, 1984 Reg.

Guide 1.97 report. Attachment II consists of replacement pages with revision change bars in the margin.

Revisions include not only the District's revised positions, but also typographical and editorial changes. All scheduler revisions will follow the District's Living Schedule procedures.

If you have any questions, please contact Jerry Delezenski at Rancho reco..

O

,be:

D. K. K. Lowe R. J. Rodriguez L. R. Keilman-R. A. Dieterich R.

. RODRIGUEZ V. C. Lewis ASSISTANT GENERAL MANAGER R.: W. Colombo (2)

NUCLEAR L. G. Schwieger (2)

C. A. Coward (2)

5. Miner (NRC)

Attachcents (E)

J. Eckhardt (NRC)

P. G. Delezenski G. C. Andognini Fourth Floor Files Licensing. Files - Plaza 50 w -

4-- r, 4 g g f- - -

Engr. Files - Plaza 50 6R l Jq v

._-_-_______--_-__=_______-_,________:______-_________-________-__----_

3 Attachment I Y'

RANCHO SECO CONFORMANCE TO REG GUIDE 1.97 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION 6

)

l. - Neutrr n Flux Requrst:

"Nettron Flux - The licensee should identify the specific portion (s) ~of

~

this instrumentation for which a deviation of Category 3 is being sought, justify these specific deviations and verify that the other portions are Ca egory 1."

psponse:

'.he District has decided not to seek deviations from Category 1 requirements for any portions of the neutron flux-instrumentation. Thus, the District will upgrade neutron flux instrument loops to Category 1 prior to Cycle 9 startup. -The District Living Schedule will reflect this addition.

2.

RCS Cold Leg Water Temperature 4

Recuest:

1 "RCS cold leg water temperature--the licensee should provide' justification

.for the deviation in the upper limit of the range."

Resconse:

The District's RCS Cold Leg Water Temperature range of 500F to 6500F provides the capability to measure in excess of 15% of the saturation j

temperature for the steam generator. The saturation temperature is less than 5600F (based on 1102.5 psig, the highest main steam safety valve setting).

An upper range of 6500F for the RCS Cold Leg Water Temperature instrumentation provides 16% margin over the saturation temperature. In addition, widening the range would reduce the sensitivity of the indication. Therefore the District maintains this range -is adequate.

(This is consistent with the B&WOG Reg. Guide 1.97 task force's generic position. )

3.

RHR (Decay Heat) Heat Exchanger Outlet Temperature Request:

"RHR heat exchanger outlet temperature--the licensee should upgrade this 2

instrumentation to Category 2."

~,'

Page 1 RG 1.97

n

.i

Response

The District will upgrade this variable to Category 2.

Temperature loops TE-26043 & TE-26044 will be upgraded for cycle 9 startup. The District's

~

Living Schedule will reflect this addition.

4.

Pressurizer Level Request:

" Pressurizer level--the licensee should supply additional analysis to

T

support the deviations from the recommended range."

Response

The District, in concert with the B&W Owners Group, is developing a generic response to this item. The District will submit its position to the NRC by January 6,1986.

5.

Pressurizer Heater Status Pres:urizer heater status--the licensee should provide the instrumentation recommended by Reg. Guide 1.97.

Response

The District, in concert with the B&W Owners Group, will develop a generic respense to this item. A submittal is planned by January 6,1986.

6.

Cuench Tank Temcerature Recuest:

" Quench tank temperature--the licensee should either show that instrumentation will remain on scale or provide 500F lower ifmit of range."

Resconse:

The District will widen the indicated range during the cycle 8 refueling cutage to include the icwer limit of 500F. The District's living schedule

.a will include this addition.

7.

Containment Soray Flow Recuest:

~:

" Containment spray flow - the licensee should identify the specific deviation frcm Category 2 instrumentation and either justify or correct the deviation."

Page 2 RG 1.97

v:

' 1

Response

Reg. Guide _1.97. defines the purpose of containment spray flow to be for monitoring ' operation of. the containment cooling system..

JAt Rancho Seco, the Reactor Building (RB) spray system consists of two separate spray trains of Jequal. capacity, each including:

RB spray. pump Spray header

-_ Spray additive tank

Speay additive eductor

~

. Isolation valves and the necessary piping Instrumentation and controls The safety features signal on high RB pressure automatically initiates.

the RB Spray System operation. Hence, for this mode of operation,-RB.

pressure is the primary variable to indicate cooling system operation.

Therefore, RB spray flow indication is a backup variable. At Rancho Seco RB pressure is a Reg. Guide 1.97 Category 1 variable.

s

~

All RB spray ' piping is Rancho Seco QA Class 1 and seismic category l.

All piping inside the RB is designed to ANSI B31.1. All reafning piping and connections to the spray system are in accordance with ANSI B31.7. The controls for the pumps and all valves which are not locked -

'~

open are Class 1 with indication in the main Control Roca. The District has performed single failure analysis on all active components of the RB spray system to shcw that the L failure of any single active component will not prevent the fulfilling of the design function following a LOCA.

Each train of the RB spray system also includes a unqualified flow transmitter which provides indication in the Centrol Rocm.

The primary indication of the adequacy of the containment cooling systems are building pressure and temperature. - At Rancho Seco RB pressure is Category 1 and RB temperature will be upgraded to Category 2.

The Class 1 pump and valve control monitors indicate RB spray system actuation.

In conclusion, the District maintains that indication of RB spray flow is a backup variable and therefore should t

be Category 3.

x.

8.

Containment Atmosphere Temperature Request:

" Containment Atmosphere Temperature - the licensee should upgrade this '

l instrument' to ' Category 2. "

I

Response

The District will upgrade temperature loops TE-52010 4 TE-52015 to Category 2 prior to Cycle 9 Startup. The District's living Schedule will reflect this addition.

i Page 3 RG 1.97 I

w.

m m

1

=

,,7 9.

Containment Sump Water. Temperature

' ' Request:

" Containment sump water temperature--the licensee should. provide category 2 instrumentat;on with the recommended range or identify-alternate instrumentation."

Response

" ' ^

According to Reg. Guide 1.97 Revision.3, the purpose for Centainment Sump Water Temperature is -to monitor operation of the Containment I

Cooling Systems.

At Rancho Seco Containment Sump Water Temperature would only be useful following a high energy.line break in containment. While containment.

sump water temperature trends may be indicative of-le. king high energy fluid and containment cooling it would be slower & less effective than other available indications. Reactor Building pressure and temperature provide more direct indication; Currently, Rancho Seco does not t

indicate or record Reactor Building sump water temperature because it is not required to mitigate the consequences of a design basis accident on a B&W designed plant. The operator is not required to take action based on this variable. However, indication of the Decay Heat / Reactor

+

Building Spray flow suction lines temperature is available with a range r..

of 0-3000F.

Reactor Building spray flow provides additional information concerning core cooling.

Back up variables are Reactor Building fan breaker status and the flow rate of cooling water to the cooling units. The-District believes this instrumentation is sufficient for monitoring the operation of the containment cooling systems. (This is consistent with the B&WOG Reg. Guide 1.97 task force's generic position.)

10.

Cemconent Cooling Water Temperature to ESF System Reouest:

" Component cooling water temperature to ESF system-the licensee should

,g provide Category 2 instrumentation!'or the NSC' temperature,.and

/

further justification for the deviation to Category 3 instrumentation for the NSRW temperature (Section 3.3.24)."

5.

Response

U The District will provide Category 2. instrumentation for Nuclear Service Cooling Water (NSCW) temperature by upgrading TI-48003 and TI-48004 during the cycle 9 refueling outage. The District's uving Schedule will reflect this addition.

4 Page 4 RG 1.97 4

Heat from the NSCW is transferred to the Nuclear Service Raw Water

.(NSRW) system in the heat exchangers. From there it is transferred to the Rancho Seco ultimate heat sink (atmosphere) via spray ponds which form a part of the NSRW.

Design outlet temperature from the NSRW spray ponds is 95cF. That is, components which are directly cooled by the NSRW are designed to accept inlet temperatures as high as 950F and function normally.

In a standby mode with no flow in the NSRW, and consequently no pond spray, the bulk spray pond temperature will be approximately the median of the caily maximum and minimum dry-bulb For the hottest month of record (August 1958), the temperatures.

estimated maximum initial pond temperature would be 86.50F (see Rancho C.,,,

Seco U.S. A.R. Section 9.4, page 20). After the operators _ start NSRW flow (and pond spray), the pond temperature will approach the wet-bulb temperature. Figure 9.4-9 of the Rancho Seco U.S. A.R. shows that for :

r.

the hattest month of record ( August 1958), the average wet-bulb temperature never exceeded 790F.

, e-Since the spray ponds provide an assured source of sufficiently low temperature coolant, temperature of the NSRW system is not a vital feedback indication of system operation. Thus, the NSRW cooling water temperature indications meet the District's understanding of the provisions of Reg. Guide 1.97 as a Category 3 parameter.

11.

Category 1 Indicators:

Recuest:

" Category 1 indicators--the licensee should provide additional information on the CRT displays."

References:

1 SMUD letter, R. J. Rodriguez to J. F. Stolz, dated September 14,1964, NUREG 0737 Supplement 1 -

Regulatory Guide 1.97, Revision 1,Section II Instrument System Description 2

SMUD 1ett:c, R. J. Rodriguez to J. F. Stolz dated July 28, 1983, SPDS Safety Analysis and Implementation Plan,Section III.C.2 and III.D

.1 khy can't dedicated recorders be used?-

Reference 1 provided the following reason for using the SPDS instead of

(..

recorders: "This approach is necessary due to space limitations in the control rocm and provides the opportunity to incorporate favorable 3

human factors into the presentation." A copy of this section is duplicated in Appendix 1 for your review.

Address the readability of the variables displayed (human factors)

Proper human factors criteria as determined by the CRDR prccess will apply to the display of all Category 1 variables. The District will modified SPDS in accordance with the Living Schedule.

Page 5 RG 1.97 e

~

O Are the displays rodundant?

Reference 2 provided the following information:

-"a.

For improved reliability and readability, two identical channels of display are provided.- Each display can monitor either the A or B loops of the plant.

b.

All parameters and graphics are displayed on two (2) color video monitors. The size of the video monitors is nineteen (19) inches.",,,

The District has seismically qualified all equipment except for the CRT's and control panel cabling. Although the system is partially redundant, power is not Class 1.

The District will modify SPDS to provide:

9 Full redundancy (2 channels)

Class 1 Power Necessary seismic qualification Indication of all Category 1 variables The District believes that use of the SPDS for the display of RG 1.97 Category 1 variables, will result in improved human factors and an integrated approach to post accident monitoring and recovery at Rancho SeCo.

Are the disolays dedicated to the real-time disolay of Category 1 variaoles?

In Reference 2, Section 5.0 the SFDS Functional Description states:

"All Category 1 variables will be implemented on the post-trip ATOG display of the SPOS" either in real time or alerts. All category 1 variables will also be available on the first page of the alphanumeric display as described below.

Also Section 2.0 states.

"When a reacter trip occurs, the display shall switch to the post-trip "ATOG" display with history trace initialized. "

.i This does not disable the system's "... flexibility of displays that allows the operator to select the most appropriate display for the existing plant conditicn." Therefore, trending is " continuously available" on reacter trip or operator request.

.j How many disolays are there?

The primary RG 1.97 Category 1 display is the post-trip AT0G display.

The first page of the alphanumeric display will also list all category 1 variables including the average of the 5 highest incore temperatures and an alert for isolation valves.

Individual incere temperatures will

.be available on the Core Pap displav and individual isolation valve positions will be available on addition alphanumeric displays. The R.G.1.97 displays use primarily category 1 variables. The remaining SPOS displays also use the category 1 variables.,

Page 6 RG 1.97

.m-

v.

..c How 'many variables are displayed per display?

The displays are still under development. The District anticipates that the primary RG 1.97 displays will be as follows:....

POST-TRIP ATOG DISPLAY

-Graph:

T-Col d, T-Hotl or T-Incorel vs. RPS Pressurel Secondary System Saturation Temperature

".L - -

Percent Powerl Percent Flowl Steam Generator Levell (operate and startup)

Alerts:

Containment Sump Levell Steam Cenerator Pressurel Reactor Vessel Level l Containment Isolation Valvesl Containment Area Radiationi i

Concentrationi Containment H2 Pressurizer Level l Auxiliary Feedwater Flowl Ccndensate Storage Tank Levell ALPHANUMERIC DISPLAY Alpha Numeric Page 1 will include:

T-Hotl T-Incore (average of 5 highest)I RPS Pressurel Steam Generator Levell Containment Sump Levell Steam Generator Prespurel Reactor Yessel Levell Centainment Isolation Valves (alert)I Y'

d Centainment Area Radiationi Concentrationi Centainment H2 Pressurizer Level l Auxiliary Feedwater Flowl Ccndensate Storage Tank Levell (I RG 1.97 Category 1 variable)

Page 7 RG 1.97

=.

E e.-

l

'.2

.g,

, Appendix 1 Section II.

Instrument Systems Description from 9100 letter, R. J. Rodriguez to J. F. Stolz, dated September 14, 1984, NUREG 0737 Supplement l' - Reculatory Guide 1.97, Revision 1 -

s

?.

k t-1 II Page 8 RG 1.97 l

es W &

de.-

7.-

II.

INSTRINENT SYSTEMS DESCRIPTION In addition to existing hardwired indicators and recorders, the District will utilize computer driven displays and other means to

~"present Reg. Guide 1.97 variables to the operator. This approach is necessary due to space limitations in the control room and provides the opportunity to incorporate favorable human factors into the presentation. The location and exact content of these displays will be developed as a part of the CRDR process.

The computer systems 'of interest to Reg. Guide 1.97 are the Safety Ij.. -~

Parameter Display System (SPDS), Interim Data kquisition and

~ Display System (IDADS), and Digital Radiation Monitoring System (DRMS).

The SPDS, a seismically qualified 1 variables. IDADS will be used to provide diverse displays (a'.g...to resolve arbiguities), i...

While DRMS provides the operator access to data fran a number of the ;+i t

radiaticn monitors installed as required by NUREG 0737.

~

Following is a description of each of these systems.

A.

SPDS The District contracted with Babcock and Wilcox (B&W) to design and deliver an SPDS to meet the appropriate requirement of NUREG 0696, Reg. GJide 1.97, NUREG 0737, and Supplement 1 to NUREG o

0737. The SPDS was designed as a diagnostic tool compatible with the Abnormal Transient Operating Guidelines (ATOG) and the Emergency Operating Procedures (EOP's). The SPDS has been designed, constructed, vendor tested, and installed. Tne SPDS is currently in a test phase for operator faciliarization and evaluatien. Testing, modification (as required), E0P revision, and training will be complete prior to Cycle 7 start-up. The SPDS will then be operational.

Future enhancements will be made to the SPDS in accordance with the District's Living Schedule. These enhancements include:

Centinuing human factors engineering during the test phase. As part of the test phase, the control rocs operators will evaluate the SPDS and suggest near-term improvements and/or enhancements to the system.

~'

Seismic qualification and dual-channel redundancy will be completed to provide the display functions for Reg.

Guide 1.97, Category 1 variables.

The SPDS will be verified and validated according to the District's V&Y plan.

Page 9 RG 1.97

8.

IDADS The main purpose of IDADS is to provide CRT displays for the Emergency Response Facilities (ERF) as required by NUREG 0696,-

and Supplement 1 to NUREG 0737. As a ' secondary ~ objective, IDADS will provide enhanced operator functions not currently available in the Control Room.

IDADS consists of a central computer system located.in the

" -T.. -

Computer Rocm.

It has various types. of input multiplexing equipment, display terminals and hardcopy equipment ir the Control Room, TSC, and EOF, and display equipment at the assembly points. Plant inputs enter the system from the following sources: the Bailey Multiplexer, the MODCOMP Multiplexer, and the Anatec Remote'Witiplexer (REMUX) System. :

The following general features are to be provided:

A.

Data Acquisition B.

Man-Machine Interface C.

Alarm Annunication D.

Radioactive Release' Monitoring E.

Reactivity Calculations F.

On-line Trending G.

Data Link to EOF Future enhancements will be made to the IDADS in accordance with.

the District's Living Schedule. These enhancements include:

A data link with the GA Technologies' DRMS Casputer so that radiation data will be available on IDADS A long term history storage and retrieval option for later interrogation of data.

Alphanumeric group trending.

Calculated values using predefined equations which can be alarmed or trended.

.d L

C.

DRMS The District co..tracted with GA Technologies (GA) to dnign and deliver a Digital Radiation Monitoring System (DRMS) to meet the appropriate requirements of NUREG 0737. The DRMS provides on-line information concerning radiation levels of selected radioisotopic concentrations within the plant prccesses and dose rate information for various areas within the plant facility.

Process measurements provide diagnostic or status information for a particular portion of the plant operation, and mcnitor releases of radioactive material from the plant environment.

1 Page 10 RG 1.97 i

..m.

.m

.m

, 3. y

.g l ^

.'F

'U DRMS consists of subsystem elements including:

RM-11 central control ~and display system Gaseous : process monitors k

Liquid precess monitors

. Wide range gas monitorNWRGi) control cabinet Strip chart recorders ce

• RM-23 portable control tnd display units High range in containment area monitor Main steam line radiation monitors The RM-ll c$mputer communicates with all the monitors using 1

three loops of redundant communications lines. Communications I..

between each monitor and the RM-23 modu,le are accomplished over j

+

a single dedicated'Hne separate from the RM-ll-loops.

4'

- The DRMS design incorporates the following features:

T Distributed data processing h

Expansion capability -

1

s Centralization of control and display 3y

- Redundancy and reliability Independence of safety related monitors

-Trending j

4 a

t i

t k

h 1

l i

4 il

'r

,4

).

i 0

- i 3

4 2

t' i

Page 11 RG 1.97

' s i

6

m,,

e

_,j e

,, x.

P

- Attachment II RANCHO MUNICIPAL UTILITY DISTRICT-M RANCHO SECO GENERATING STATION

! '.t _

2 UNIT NO 1 t

.i.

REGULATORY GUIDE 1.97 POSITION

• p' g

$e REVISION 2 (CORRECTED PAGES ONLY) i i

OCTOBER 1985

.k.-

n 4

e C

f r

h f

I a

w

-~s.- 6

..... m

[_'

~.,,

<T

}

(

• ' =

e-is!! 'ti

' ;.dtM j

i.

Var.

Variable Per SMUD SMim Conpiter NRC

'SMUD

,,

.. 9 No.

R.G.1.97 Rev. 3 Tag Nos.

Ca t.

Display Range Range

, Con =ren ts

/. t ~;52,'

i

" f t. *dh'}

l s

l TYPR H VARTADIfPS

'. g '. g$

.t

,sr

^"

l 6

ileutron Flux

'Ib De 1

SmS 10-6 to Co wly Living Schedule

~.

I i

(Category 1)

Assigned IrmDS 100%, full l

/..U.

power

(

7 Control Rod Item 1 on 3

SmS Full In Ibt Co wly.

J,p Position Il2PS IlmDS Full In (Category 3)

+2

.'.s

.:. ll 8

RCS Soluble Doron AE-22202 3

Sms 0-6000 ppn Cowly Concentration IDADS

~

(Category 3)

~ -

r !,

~9 RCS Cold Leg Water TE-21023 A,0 3

SPDS 50-4000F Cogly.,

Temperature TE-21024 A,0 IDADS (Category 3)

.+

10 RCS Ilot Leg Water TE-21030 1

SPDS 50 to 7000F 120 to Living Schedule Temperature TE-21033 IDADS 9200F See Same as Variable 1

' lj l Q3 '

. 6*#. '

(Category 1)

Note 10 '

11 RCS Cold Leg Water TE-21023 A,B 3

SPDS 50 to 7000F 50 to

~

Temperature TE-21,024 A,B See IDADS 6500F See same as variable 9 (Category 1) tbte Ibte 11 11

<. ' ~

y

,e Rev. 2-16 l

=

.a

w i.a

.u *.: Lir,

s..ti. a.

. ;.p *,.

. i.'t, ' h.!,E Var.

Variable Per SMUD SMUD Conpiter NRC SMUD w.-

u.,

. r.i.j N.....;;., ;r No.

R.G. 1.97 Rev. 3 Tag Nos.

Cat.

Display Range Range Consnents,

i

.,.}

.- s:7 TYPR C VARTN1IES i.

T 21 Core Exit See Variable 1

SPOS 200 to Conply Living Schedule.

.- *?

,, i 3 l

i Tenparature 13 ItW1S 23000F Same as Variable 13

.. - e (category 1)

.~

• ,,,,'f;

. - =

. ':p' 22 Radioactivity Hone M/A 1/2 Tech N7A See Variable 23

~

Concentration See Spec to 100 (Category 1)

Note x Tech Spec 22 23 Analysin of PASS 3

10-6 to 10-6 to

~ "

Primary Coolant 10 C1/ml 3.75C1/mi l '.'

(Category 3)

See Note l.

/

23

'24 RCS Pressure

1Y-21050 1'

SPDS 0-3000 Conply same as variable 2 d ;..

(Catogory 1)

IT-21051 IDADS palg

... ~ s,'.?lf l'..5,.h

.. d!

M.' ~..

A 25

. Containment IT-53621 1

SPDS

-5 psig to Conply.

. Same as Welable 18 -

n Pressure 14-53622 IDADS 3 x design l-(Catcgory 1)

(177 psig) 26 Containment LE-26112 C,D 2

SPDS

'Ibp to Conply

,Same as variable 3 Sune water Level LS!!-26112 A,B IDADS Dottom See lete

- ;s (Category 2) NRW LE-20509 A,B 1

Plant 17 i

(Category 1) Wide-LE-20510 A,n Specific s

y 19 Y

' s Rev. 2 3

f.

,.',,r;-?p.' n

.u

..-;.w:

.-A.t,e

[

.c

,.r Var.

Variable Per

.SMdD SMUD Conputer IIRC SMUD

['.'.,7 ' l *. '.

i' No.

R.G. 1.97 Rev. 3 Tag 11os.

Cat.

Display Range Range

' - !{ 'f',~.,'J. a Coments h

TYPR C VARTARTFS (continued) 27 Containment R-15049 1

SPDS 1 to 104 Conply Living Schedule I

Area Radiation R-15050 IDADS R/hr

?

(Category 3)

DRMS

~,

I 28 Effluent R-15004 3

10-6 to

.Conply.

Radioactivity 10-2u (Category 3)

C1/cc

'9' ii 29 RCS Pressure PP-21050 1

SPDS 0-3000 psig Conply

" Same as Variable 2 b.~

(Category 1)

PP-21051 IDADS 30 Containment AE-53011 1

SPDS 0 - 1 0 % 112 Conply See tiote 30 II2 Concentration AE-53812 IDADS (Category 1) 31 Containment PP-53621 1

SPDS

-5 ps'Ig to Conply Same as Variable 18

• b.~~...;t Pressure PP-53622 IDADS 3x design (Category 1)

(177 psig) 32 Containment N/A N/A 10-6 to N/A Effluent' Rad.

See 10-2u C1/cc.-

.~

(Category 2)

Note 2i 32

'. ]

~-

,, 'I 33 ECfluent R-15044 2

SPDS 10-6 to-Conply 10 u C1/cc d

3 Radioactivity R-15546A IDADS (Category 2)

DRMS I;'h 20 Rev. 2

• 1 s....

c es..

q

• 1..'

• ' 5..:..>.

• ei d.' .i ;,'

~

Var.

VarIabie Pcr SMUD SMllD Conpiter !!!!C SMUD Mo.

R.G.1.97 Rev. 3 Tag flos.

Cat.

Display Rangs Rango

,Coments

". " J.T.' 4;* (t 1

e TYPR D VARIAnLF.S itilR System FT-26003 2

SIWI 0-110%

Conply 34 Flow PP-26004 IDADS Design (Category 2)

Flow (3000 gpm)

.. d 35 RIIR Ileat TE-26043 2

IDADS 400 to C6npfy

.Living Schedule b

c Exchanger Outlet TE-26044 3500F

- Tenporature

• I!

(Category 2) 36A Accum. Tank LT-26505 2

SPDS.

10 to 90%

2 to_81%

Invol.

LT-26506 IDADS See Ibte 36A (Category 2)

LT-26507 LT-26508 36B Accura. Tank '

FP-26501 3

IDADS 0-750 pelg Conply

• Pressure PP-26502 See

... f~ s' y

. i *.*.

(Category 2)

PP-26503 Note

.. ;p[.]9; PP-26504 36n

• [g1 1

37 Accum. Iso.

11V-26513 3

Closed or Conply-

,7 Valve Position IIV-26514 See Open (Category 2)

Note 37

'30 Doric Acid N/A N/A 0-110%

N/A Charging Flow See design flow

~*

(Category 2)

Hote 30

..y 7. \\,.

-ti l

Rev. 2 21 g

.. i...

c.

e

" ' .i}'

?

d3.

J.

H-i

...^ ;

-t'.

Var.

Variable Per SMUD SMUD Conputer ImC SMUD No.

R.G.1.97 Rev. 3 Tag Ibs.

Cat.

Display Range Range Comnents

...' ",1 I

l TYPE D VARIABLES Cont'd$

45 Pressurizer MCC S2A2 2

Electric On-Off IIcater Status MCC S2B2 Current

. See !bte l

(Category 2) 45 j

46 Giench Tank LT-21905 3

'Ibp to 0-10 ft.

Invel Bottom Upper IIalf (Category 3)

(0-23'5")

See Ibte 46 47 Quench Tank TE-21001 3

500 to 500P to' Living Schedule d.

Tenrerature 7500P 6000F See l

(Category 3)

Ibte 47 1

40 Quench Tank 14-21920 3

0 to 0-200 psig i

Pressure design See

~

(Category 3) pressure Ibte 40 (235 psig) -- /

N 49 Steam Generator LT-20507 A,D 1

SPDS From tuid 6-61 9" Living Schedule Level IN-20500 A,D IDADS Sheet to See Same as variable 4 (Category 1)

Separators

' tbte 49 y

50' Steam Generator IP-20544 A,B 1

SPDS From A'IM 0-1200,

Living Schedule Pressure 14-20545 A,B IDADS pressure to psig

....' Same as.Vhriable 5 *

(Category 2) 20% above See Iowest tbte 50, -

nacety valve setting D'

~

51 Safety Hellef XE-20533 N/A IDADS Closed /

Open/tbt',

Valve Ibsition XE-20534 See Not Closed Open See-(Category 2)

XE-20544 lbte tete 51 to 20559 51

't, XE-20571 A,D,C a

}'-

XE-20562 A,D,C i-iI ei... -

r 23 Rev. 2

-m a

-t.

. T,! h:.1.?NH F.

. i:c, var.

Variable Per SMin Iki.

R.G. 1.97 nev. 3 SMin.

ompio:er sinc Ship

.: s

.. 42.,e l **:

Tag thin.

Cat, nitsplay Pango Rango-Crnements f:l;*',(

'ITEILILVAllIADLES Cont;hl

<e s

52 flain l'ecdwater 11/A II/A 1 F]ow 0-1101 11/A j

(Category 3) see c

design flow 8

Ible

'* c ?

52 51 Anx. or Drer.

Pt'31902 1

SPn't 0-1101-Conely

'.'* d.

FecAinter Flow PI'31901 IlW)S Denign Flow (Category 1)

PI'31n02 riu3t001 (1120 gon).

at 975 polg) 54 Contlennate Storage T!!'1'i409 1

Tank thter Level.

!!!' 3 5111 0

' SP8Y1 Plant (0-50')

I.tving setiedule (Category 1) ilWU Upecific t

55 Containinent rt'29t03 3

Spray P. low PI'29104 See Congly

,h *" I 0-110%

(Category 2)

Design Flow.

tbte-(1500 gpn) 55 56

^ fleat Renoval by A-500 A,D,C,n 2

.,,, i CFilft Syst:em A-5.12 A,11,C.t)

(On-off

, see 7bte 56 Plant

,s (Category 2) t'pectflo status)

,... ; ;'t '

-57 Coni:aInnent -

Tfs-52010 2

IIWrt 40 to

.Conply J-ELiving Schedule,*

, k.'+*,*,/

Atenno. Tenp.

'J15-520t 5 (Category 2)-

4000P-

• T : *.."'l i '..

i,,

e

.'3

=

24 g.

Rev. 2,. ' ' 7-[

~

W s

~.

.. ~

• t 5,.

(

d

.1

\\

C

..y,>.,,

D

m

[-

l ; t-c.. ;3,m I

r.

.H1 Va r.

. Variable Pcr St10D SMUD Conputer NRC

.C.'!UD l

Mo.

R.G. l.97 Rev. 3 Tag Mos.

Cat.

Display Range Itange Coninents

.l l

l.

l.

'IYPT: D VallIN)TES Cont'du t

i 50 Containment Sunp N/A II/A So to N/A l

Water Tenocrature See 2500P l

(Category 2) tbte 50 y

l 59 Plakeup Flow - In N/A 11/A 0-110%

N/A (Category 2)

See Design Flow tbte 59 60 Letdown Flow N/A N/A 0-110%

N/A

- Out See Design Flow.

(Category 2) tbte 60 61 Volume Control N/A N/A ibp to N/A,

Tank Level See nottom (Category 2) tbte 61 l

62A Conp. Cooling Water _

TE-40003 2

IDAnS 40 to.

Conply Living Schedule d.

Tenp to ESP Sys.

TE-48004 2000P (Cr.'. 2) (NSCW) c i

l Conply},,,

..a,

. 'i cm l

62n Conp. Coollng Water TE-47203,4 3

T'MDS 40 to

'g.

Tenp. to ESP Sys.

TE-40013,4 See 2000F,',

,- ;j.

(Cat. 2) (NSnW)

Ibte 62n

',' ?

, e,

.s 7,

\\

n..

t',

25 s.

Rev. 2 7

.t l

?

9'N*

4p 4

e

.x l.

V - TABULATION NOTSS

+

s.

. ~. '.

variable' Exclanation 2

~

... s,

.....a..,..

. ~

.w i

- mm

. ~..

a -

. :~... -

s,...,... r r-s.

Y. 1

!~

10 The low end of the range for RCS hot leg temperature is not 7:.

important to pcst accident monitoring. ; Cold shutfown is defined in the Technical Specifications as less than 2000F.

The RCS temperature between 500F and 120CF is cold enough.for -

refueling and, therefore, is a safe condition.:

11 -

RCS Ect Leg Te=perature (variable 1),-RCS Pressure (variable'

2), Subcooling Monitor (variable 15), Coolant Inventory

- ce r s(:

(variable 14), and Core' Exit Te=perature (variable 13) provide the RCS para:eters necessary for function detection, acco=plish=ent of =itigation, and long-ter: surveillance required by the Category 1 guidelines.

Reg. Guide 1.97 lists cold leg wate: tamperature a's a Category 1 (key). variable and ccre ezit temperature as a Category 3 (backup) variable for the core cooling functica.

Ect leg and cold leg temperature indications r.ay not in all cases provide va' lid infor=ation on the status. of core cooling.

Since they are located in the RCS loops and not the reactor vessel, there: must be either forced or natural circulation flew through the steam generators for their

~

indications to be representative of actual core conditicas.

g Also, due to the proxi=ity of _ the cold leg RTD's to the E?I

.,t nc:=les, E?I flow may significantly affect the cold leg temperature indication particularly in the absence of forced.

?

T RCS flow.

Incore te=perature monitors provide'a more direct indication cf core cooling independent of whether.or not y

there exists coolant flow through the loops.

For these reasons, core exit temperature is -the -key variable for monitoring core cooling and is qualified to Category in requirements while RCS cold leg temperature serves as a backup variable and is qualified to Category 3 requirenents accordingly.

A Thecexisting insuallation of the Cold Lee ins:ruments meet or exceed each of the category 3 require =ents and, therefore, are adequate to. verify system operation for reactivity control.

(This is concistent with the BriWCG ' Rec. Guide 1.97

~

task force's generic position.)

~

f 31 Rev..~. _... _ -. -

e 1'

w e

w-my

-1

.-y

'y iv tw---

• -ee-s~g-

.g y-e-3+~g 9g W

ww=*=.-

e..'-

y g

~

..l

.i

-Varieble Exclanation

.. 3 2..

. As ta ' result of ' NURIG 0737, Clarifcation II.E.4.2 (attachment.

s 6), the District has coc=itted te maintain the Containment Purge,and' Ecualizing Valves in the fully closed position and.

1 with the air source removed except during cold shutdown-(accepted by the NRC in the. letter dated 3/15/84, Stolz to Mattinoe).

i In addition, the position of these valves is checked once every 31 days.

..-V -

.?

The Containment Effluent Radiation' Monitors are only. of :.:.

..cr c ".'d.-".': 1 benefit if there.is.a pathway to the environment through theic' :

Contain=ent Purge Valves or Equalizing Valves.

Since - these. -"....',

valves. are normally closed per Technical. Specification,' and -x. -

p.

only. opened during cold shutdownf and.since they would.not be

t cpened in a post' accident situation, the Containment Effluent..

Radiation (and flow) monitors are not necessary for post acciden. monitoring instrumentation at Rancho Secc.

m

..: /.l < :.

2 36A The level range is acceptable because it c'easures above the '

r normal operating range of the tank.. The high alars is at.

13.3 feet (95% of indicated range).

The normal fill level:is 13.0 feet (93% of indicated range) and the low alarm -is set as 12.7 feet (91% cf indicated range).

The Core Flood Tanks would not be filled above this level.. Therefore, the level.

range is adequate to monitor operation.

(This is consistent with the B&WCG Reg. Guide 1.97. task force's generic positicn.)'

363 The Core Flood Tank (CFT) pressure instrunents are used as back-up information.

The key. variable to ' indicate proper operation is CFT level (variable 36A).. Therefore,CFT pressure is classified as Category 3.'-

(This. is consistent with the B&WCG Reg. Guide 1.97 task force's generic pasition.)

e' 8

34 Rev.-2 e.,*.&m

• . * * > - = eeums.~ e -

~e-

+--

w vgrp qgmv g*

e ew---*3-"ir 9-1 m

y v =

N-ve sw--

y' g

e-w

-9g*

7

._,~~

(

~

L.*J ~.va dable.

ExM an a Mon

~

51 These' instru=ents were installed to meet the ; requirements of

-- the Reg. Guide l'.97 category classification is not'NUREG applicable.

Since the main steam ' flow is not a measured variable at Rancho Seco, acoustic leak detection instruments were installed on the-Steam Generator Safety Valves and the At=ospheric Dump Valves (ADv's). Although no specific

'C. ' _..

those approved by the NRC for installation on.the pres safety valves and the pORV, were used..

(See NRC-SMUD letter : -

dated May 1,.1980 re:

Evaluation oflicensee's Compliance.. :

with Catecory "A" Items of NRC Recommendations.Resulting from -2:.:.

TMI Lessens - Learned, Item 2.1.3a)..This system provides :.

back-up information to Steam Generator. Pressure which is the :..

primary variable to shew secondary system integrity and is a.. - -

Category 1 variable (variable 5).- :(This is consistent with the B&WCG Reg. Guide 1.97 task force's ge:neric position.)..

Each valve.is monitored by two accustic steam flow cetectors.

Indication in the centrol room is labeled Valve open/Not Open.

~

. c.

The accustic 'detecti',n system does not monitor valve position

~

directly.

Ecwever, it is this use at Rancho Sec0 reliable and has been accepted for^

(accepted by the NRC in the letter dated 5/1/80by the.NRC for PORv's Matti=ce).

Reid to 52 mitigation of any design basis accident.The availability of Ma instru=entation te detect the less of main feedwater is Safety grade available _ and is used by the Reactor Protection System (I?S) to develop an anticipatory reactor trip.

However, the

=easnrecent of Main Feedwater Flow in a post accident.

situation re=ains ncn-essential.

This parameter is, therefore, not considered a part of the Rancho Seco pcst s

accident monitoring instrumentation.

55 Reg. Cd.de 1.97 dem the pt._ pose of ccorehe spray flaito be for c:enitoring cperation of the cenrah t cooling syst s.

?

At Rancho Seco the Reactor Building (RB) spray systs consists of tw separate spray trains of ecual capacity,.each including:

valves and the necessary piping; Instruantation and 2

We safety features signal en high R3 pressure surme%11 the RB Scray System operation.

i 7 nitiates Hence, for. this. mode of operaticn,-RB pressure"is t'e pri=ary variable to indicate ecoling syste operation.

Werefore, R3 spray ird% ica is a backup var'able.

t At b~'*n Seco R3 '

pressure is a Reg. Guide 1.97 Category.1 var'2ble.

NOIE 55 CDNTET.E5 ON PAGE 38A 38 Rev. 2 I

• w+=

=e.

w =ep e e a w

w---"

y-y

+

y, v-

-areg yW-p-t w

a-f=o-*

+9---

ur

,vw,-e a-w w-

-+,- w y-

--r

'va s.icb1.

rxelanatien M1 R3 spray piping is Rancho Seco QA Chss 1 and seismic category 1.

55 All piping inside the R3 is designed to AMI B31.1 All r e ining piping and cennections to the spray systes are in accordance with ANSI

.E31.7.

'Ibe centrols fari de pt=ps and all valves which are not locb. d coen are Class 1 with indication in the main ecntrol rect:. 'Ibe District bas perfor=ed single' failtre analysis on all active cccocnents of the RB -

spray system to show that the failure of any single active cc::pocent will not prevent the W4114"o of the design ftmetica following a i

IOCA..Each train of the R3 spray system also includes a ocn qtaliN4 - -

flew transmitter which provides indicarien in the Control Rocn.

4

'Ibe'pri=ary indientien of the adequacy' of tM cene>4-t cooling LU

=-

systa=s are building presstre and tempet:=e. At RancM Seco RB r-presstre is Category 1 and 33 te=perature vill be uog aded to Category s

2.

'Ibe Class 1 pt=o and valw control monitors indiente RB spray systen ac* :atien.

In ccnclusicn, the District mainesim that iMfc="im of RB spray ficw is a bacicm variable and therefore shculd be Category 3.

1 I

l l

l i

3

?

l l

}

I i

)

j i

38A i

Rcv. 2

(

m m.-

p g.,......y, g a di. -

.r.n,-

<er.

s v

.v:

~

Sasurement of heat removal is indirect. ' Class 1 On/off lights direc o

56 indicate power to the fans.

p D

^

2 58 l

According to Reg. Guide 1.97 Revision.3, the purpose for cmeain"=at Suco Water Temperature is to monitor operation of the Cmemi-t -

Cooling. Systems.

.[

.;, c.

At Rancho Seco Cme =4m="t Su::n Water Tempe'rature iculd inly be useful 1 i:

following a-high energy line break (EEUW in conPeinman".

b.

While. -

cenr24w=nt sur:n temperature trends may be indfraHve of leakin energy fluid and conPainmant cooling it imuld '.;e slower Is less *g high n 4

f#a"Hve -

than other available indications.

Reactor BdMng pressure and 2

~

temperature provide more direct indication.

7 not indicate or record Reactor Building sua Carrently; Rancho Seco does -

1

~

-it is not required to mitigate the cmaag p water te=oerature because of a design basis accident on a-BS74 dacignad plant.

'Ibe o J-Ibwever,perator is not required to take -

actim hacaa on this variable.

indte=Hm cf the Deezy Eeat/ Reactor Building' Spray flow suctim lines L;--Mme is available 7 with a range of 0-3000F.

s, Reactor Building spray flev provides =Ad4Hm=1 infwh concerning cc:a cooling. Back un variables are Reactor bd1A4ng fan breaker status and the ficw rate of cooling water to the coolingLunits.

N-

.'Ihe Dist:ict believes this instri-entation is snF of the e-*=4me,t cooling systa=s.

4e4=n* for monitoring the coe:ntion

('Ihis is censistent.with the BS&OG Reg. Guide 1.97 task force's generic positico.)

i 1

39

'"he Makeup Systa= at Ranche Seco supports varices p:ccesses

}:

Important te the Reacte: Ccclant Systes during norsal i

cperatien.

In addition, several ecmcenents of the Makaus

~

j a cual function of makeup during ac :al cperatica an e

i pressure injection f functions are separa'cliewing an accident.

Rowever, the I

patnways te the RCS.-.e and involve separate water sources and not essential pathways for the citication of any desic:Nc::al =akeu j j ace: cent.

basis the ner:al makeup ficw pathway and its measure =ent has n ia

'3 function e,ssential to the mitigation of-anv~ desien basis 14 accident.

Ranche Sece pcst accident recuired signal."'herefore, this para L:

accident ' essential signals which measure hich cres'sure

('"he - ecs't i

injection flow are covered 'elsewhere by variable 39 )

4 60 Maintaining Reactc: Coolant System ' letdown to the Makene and Furificatien system is -not essential to the citica:icn of anv i.

desien basis accident at Rancho seco.

j '

initiated, letdown ficw-is isclated.the' safety Features Actuation s that i

is.

{

therefore, not essential to post accident =enitering and isLetdown ilev out l's,-

Rancho seco.not censidered a part of the post accident instrenentatica at t.

Y i:

39

^

k Rev. 2

-We e.,.p.e_

a y

(. ~,,,...

w

{

lw,

.. ~,.. *.

l Variabla heleaHon- :

_ b.,,,,

' The Rea'ctor Coolant System Volume Cohtrol Tank (F.ake Up Tank).

61" at Rancho Seco is a. part 'of the' N.akeup and Purification -

System.

It, functions. as a. source of water. for the RCS F.akeup rumps in their no: mal cperating-mode, as-a 'nixine buffer for normal additions of concentrated boric acid.and decine:alized water-to.the RCS, as the process interface fo': addition of Eydrogen to the RCS for oxygen control, and as surge volume for small fluctuatiens of RCS volume due to minor changes fin normal RCS cperating parameters.

, ~..;,

None of these functions are esential to the mitication of any

~

~

C t '-

design basis accident.

Also, the Volume Control' Tank does -

t

~

not act as an fessential pathway for the addition cf coolant -

chemicals recuired to citigate any design basis accident.

c:

~

• ~

~

~

--:-~,

The Volume' Control Tank level instrunentation' at Ranch

• Seco'.

c i

is, therefore,- not considered-a part of post accident f

monitoring i.3strumentation.:

<~ -

.c

.~.

623 Feat from the NSG is transferred to the Nuclear Service' Raw Water.

(N5 W) system in the heat exchangers. Frca there it is tr=#med to-the Rancho Seco ultimate heat sink (atmosphere) via spray poods which - /

a fo = a part of.the NEM. Design outlet e-a f:ca the NEN spray. -

.c..:. -

ponds is 95CF. 'Ihat is, wts which are directly cooled by the -

2 -

N5W are designed to accept inlet ea =ratures as high as 950F and

- f=ction nor ally. In a standby mode with no flow in the NEfi, and u-censequently no pend spray, the bulk spray pmd ta=oeratu:e will be -

app: r# tely the ce/4 = of the daily==rbm and =4n4-dry-bulb te=peratures. For the hottest unnth of record (August 1958), the =

es-d W cs-d - inic4=1 Seco U.S.A.R. Sec-den 9.4,pcca tecoerature would be 86.50F (see Rancho page 20).. After the operators sst N5W flow (and pend spray), the pond ta=perature vill approach the vet-bulb te=perature. Figure 9.4-9 of the Rancho Seco U.S.A.R. shows that for the hottest month of record (August 1958), the average wet-bulb e-erature never exceeded 79CF.

~

Since the spray pends provide an assured source of an###rfaetly low te=perature coolant, te=oerature of the IG51 system is not a v51

,p feedback ira #catica of system operation. r'Ihm, the NSW cooling water tecoeratu:e indir=e4cns meet the District's =lamad -

prc'isiens of Reg. Guide 1.97 as a Category 3 par =arer.,, of the v

s t-63 Component Cocling for Safety Features conponents at Rancho Secc is provided by the Nuclear Service Cooiing '4ater and Nuclear Service Raw Water. Systems.

Flcw.indicatica fe: these sys'tems is classified as a Catecory 3 parameter because they are used for dizenestic purposes only.

Primary indication of system operation is provided by Class 1 pung status and valve position indications.

63 Fressure indication fer. the Radioactive Gas Eoidup Ta.ks has a tange of 0 - 160 psig.

160 psig cis.110% of the relief valve setpcint and 107% of the design pressure cf the vessels.

Since relief cccurs at 145 psig, the Dist:ict considers this range adecuace.

40 Rev.12 w

-e w

_