ML20154S009

Forwards Response to 860224 Request for Addl Info Re Conformance to Reg Guide 1.97 Concerning Emergency Response Capability.Meeting During Apr 1986 Suggested to Answer Remaining Questions.Revised FSAR Pages Also Encl

ML20154S009
Person / Time
Site:	South Texas
Issue date:	03/26/1986
From:	Wisenburg M HOUSTON LIGHTING & POWER CO.
To:	Noonan V Office of Nuclear Reactor Regulation
References
CON-#286-585, RTR-REGGD-01.097, RTR-REGGD-1.097 OL, NUDOCS 8603310273
Download: ML20154S009 (48)

Text

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i. 7,a-u-,. m . ,-i o =~ u March 26, 1986 ST-HL-AE-1630 File No. G9.17 Mr. Vincent S. Noonan, Project Director PWR Project Directorate #5 U. S. Nuclear Regulatory Commission Washington, DC 20555 South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50-499 Rr:monses to NRC Request for Additio:ial Information Regarding RG 1.97

Reference:

Letter - N.. P. Kadambi to J. H.Goldberg, dated February 24, 1986; South Texas Project Emergency Response Capability - Conformance to R.G. 1.97, Rev. 2

Dear Mr. Noonan:

As indicated in FSAR Appendix 7B, the STP implementation of Regulatory Guide 1.97 requirements was performed in an integrated fashion with the Control Room Design Review, using the WOG Emergency Response Guidelines and the guidance of appropriate NUREG documents. This integrated approach was presented to NRC in December 1983 (meeting notes ST-AE-HL-90317, NRC letter dated February 16, 1984) and discussed during several subsequent meetings with the staff. Review of STP with consideration given to this integrated approach will show conformance to NUREG-0737, NUREG-0737 Supplement 1 and RG 1.97.

The attachments enclosed provide STP's response to the referenced letter. We feel that this supplemental information is adequate to permit your review of STP conformance to RG 1.97 to be completed. In order to facilitate your completed review of RG 1.97 conformance, we suggest that a meeting be held during the month of April,1986 to answer any remaining questions. We suggest that the appropriate members of the INEL review team also be present at this meeting, so that conformance to RG 1.97 can be established to the agreement of all parties involved. Members of our Licensing staff will be contacting the NRC Project Manager to arrange the subject meeting.

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8603310273 860326 A PDR ADOCK 05000498 A PDR

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ST-HL-AE-1630 liouston Lighting & Power Company File No.: G9.17 Page 2 i

i If you should have any questions on this matter, please contact Mr. M. E. Powell at (713) 993-1328.

Very truly yours, M. R. W enburg Manager, uclear icensing THC/yd Attachment A: Item-by-item responses to eich of the exceptions identified in the INEL report sent by the referenced letter.

Attachment B: FSAR Table 7.5-1 (Amendment 53, in process), marked up to show changes required, particularly in response to INEL report exceptions.

Attachment C: Description of reasons for changes in Amendment 53 FSAR Table 7.5-1 (1.e., changes from current pages of Table 7.5-1 to Amendment 53 revision); letter references for recent FSAR updates pertinent to this submittal; change in FSAR Section 7A.II.F.1 regarding containment water level sensors.

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, r ST-HL-AE-1630 llouston Lighting & Power Company File No.: G9.17 Page 3 cc:

Hugh L. Thompson, Jr., Director Brian E. Berwick, Esquire Livision of PWR Licensing - A Assistant Attorney General for Office of Nuclear Reactor Regulation the State of Texas U.S. Nuclear Regulatory Commission P.O. Box 12548, Capitol Station Washington, DC 20555 Austin, TX 78711 Robert D. Martin Lanny A. Sinkin Regional Administrator, Region IV Christic Institute Nuclear Regulatory Commission 1324 North Capitol Street 611 Ryan Plaza Drive, Suite 1000 Washington, D.C. 20002 Arlington, TX 76011 Oreste R. Pirfo, Esquire N. Prasad Kadambi, Project Manager Hearing Attorney 4 U.S. Nuclear Regulatory Commission Office of the Executive Legal Director '

7920 Norfolk Avenue U.S. Nuclear Regulatory Commission Bethesda, MD 20814 Washington, DC 20555 l

4 Claude E. Johnson Charles Bechhoefer, Esquire i Senior Resident Inspector /STP Chairman, Atomic Safety &

c/o U.S. Nuclear Regulatory Licensing Board Commission U.S. Nuclear Regulatory Commission P.O. Box 910 Washington, DC 20555 Bay City. TX 77414 Dr. James C. Lamb, III M.D. Schwarz, Jr. , Esquire 313 Woodhaven Road Baker & Botts Chapel Hill, NC 27514 One Shell Plaza Houston, TX 77002 Judge Frederick J. Shon

, Atomic Safety and Licensing Board J.R. Newman, Esquire U.S. Nuclear Regulatory Commission i Newman & Holtzinger, P.C. Washington, DC 20555 1615 L Street, N.W.

l Washington, DC 20036 Mr. Ray Goldstein, Esquire 1001 Vaughn Building Director, Office of Inspection 807 Brazos j and Enforcement Austin, TX 78701 j U.S. Nuclear Regulatory Commission Washington, DC 20555 Citizens for Equitable Utilities, Inc.

c/o Ms. Peggy Buchorn T.V. Shockley/R.L. Range Route 1, Box 1684 Central Power & Light Company Brazoria, TX 77422 P.O. Box 2121 Corpus Christi, TX 78403 Docketing & Service Section Office of the Secretary H.L. Peterson/G. Pokorny U.S. Nuclear Regulatory Commission City of Austin Washington, DC 20555 P.O. Box 1088 (3 Copies)

! Austin, TX 78767 Advisory Committaa nn Fanetor Safeguard J.B. Poston/A. vonRosenberg U.S. Nuclear Regulatory Commission City Public Service Board 1717 H Street P.O. Box 1771 Washington, DC 20555 San Antonio, TX 78296 Revised 12/2/85 i

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ATTACHMENT #

ST-HL-AE- /lo30 PAGE I OF.20 Attachment A This attachment provides item-by-item responses to each of the exceptions identified in Section 4 of the INEL report attached to NRC letter dated February 24, 1986. Where exceptions are closely related, they have been grouped and responses provided for that group. l l

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ATTACHMENT 4 ST.HL-AE I630 PAGE S OF JO INEL Report Exception:

1. Range requirement deviation--the applicant should provide the range monitored for the twelve variables listed and justify any deviation from the regulatory guide (Section 3.3.1).

Response

The ranges for the identified variables are provided below:

Title ,

Range

1. SG Water Level (Wide Range)

Top Tap - 604" above tube sheet Total Range - 592" 4" above top of primary separator Bottom Tap - 12" above tube sheet Top of tube sheet to top of SG - 769"

2. SG Water Level (Narrow Range)

Bottom Tap - 425" above tube sheet Total Range - 179"

3. Pressurizer Water Level: Volume Span Low Level Tap 147.7 ft3 Upper Level Tap 2002.3 ft3 Total Volume 2100 ft3

4. Refueling Water Storage Tank Water Level: Total Range - 384" Bottom Tap 3/8" above tank bottom Centerline of Supply Nozzle - 2'-11-3/8" above tank bottom Centerline of Overflow - 32' 4-11/16" above tank bottom

5. Auxiliary Feedwater Storage Tank Water Level: Total Range - 514" Bottom Tap - 6" above tank bottom, at centerline of pump suction Upper Range - centerline of tank overflow

6. Auxiliary Feedwater Flow: *0 - 700 gpm per SG

7. Volume Control Tank Water Level: Volume Span Low Level Tap 72 ft3 Upper Level Tap 528 ft3 Total Volume 600 ft3

8. Main Feedwater Flow: *0 - 5.0 x 106 lbm/hr 1

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• ATTACHMENT A ST-HL AE IG30 PAGE 3 OFao

9. Containment Spray Flow: *0 - 3000 gpm

10. Component Cooling Water Flow to ESF Components:

• Pump Discharge 0 - 20,000 gpm

• RCFC 0 - 2500 gpm

• RHR HX 0 - 7000 gpm 11.-Residual Heat Removal System Flow: *0 - 4000 gpm

12. Unit Vent Flow: *37,000 - 290,500 cfm

• Table 7.5-1 has been revised to reflect this information (see attached annotated pages) and will be incorporated in a future FSAR amendment.

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ATTACHMENT #

ST HL-AE /4,30 PAGE V 0F .to INEL Report Exception:

2. RCS soluble boron concentration--the applicant should provide the information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable, identify any deviation and justify those deviations identified (Section 3.3.2).

Response

The South Texas Project Post-Accident Sampling System provides the RCS soluble boron concentration measurement; this measurement meets the Regulatory Guide 1.97, Rev. 2 Category 3 requirements. The PASS is described in FSAR Section 9.3.2.

Table 7.5-1 has been revised to reflect this information (see attached annotated pages).

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ATTACHMENT 4 ST-HL AE- /43o PAGE 5 OF.23 INEL P.eport Exception:

3. Containment isolation valve position--the applicant should provide Category 1 instrumentation for this variable or identify and justify any specific deviation (Section 3.3.6).

Response

~

The appurtenances and power supplies for the containment isolation valves, as noted in Table 7.5-1, meet the intent of Regulatory Guide 1.97 Category 1 instrumentation. For isolation valves in series, a single indication on each valve is sufficient to satisfy the requirements of Regulatory Guide 1.97 when those indications are powered from different trains.

Containment isolation valve status conforms to Regulatory Guide 1.97 Category 1 instrumentation criteria, except for valve indication. There are no other deviations from the Category 1 instrumentation.

Table 7.5-1 has been revised to reflect the above information (see attached annotated pages).

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ATTACHMENT A ST HL AE- /6,3o PAGE 6 0F Jo INEL Report Exception:

4. Analysis of primary coolant (gamma spectrum)--the applicant should provide the information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable, identify any deviation and justify those deviations identified (Section 3.3.8).

Response

The South Texas Project Post-Accident Sampling System is used to provide an l RCS sample for analysis of primary coolant (gamma spectrum); on-site laboratory instrumentation is used for the analysis and meets the Regulatory Guide 1.97, Rev. 2 Category 3 requirements.

Table 7.5-1 has been revised to reflect this information (see attached annotated pages).

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• ATTACHMENT A ST-HL AE-/63o PAGE 7 OF A INEL Report Exception:

5. Accumulator tank level and pressure--the applicant should justify the deviation in the pressure range; the applicant should install accumulator tank level instrumentation that meets the recommendations of Regulatory Guide 1.97 (Section 3.3.12).

Response

Accumulator Tank Pressure The range of the accumulator tank pressure indicator is adequate to monitor any expected pressure within the accumulators. The maximum pressure allowed by the plant Technical Specifications is between 586 and 679 psig (Technical Specification 3.5.1). Furthermore, the accumulator discharge isolation valves are locked open during operation. Hence, any malfunction of the two series check valves would be immediately indicated to the operator in the control room. Finally, the accumulator is protected by a spring loaded safety valve with a setting of 700 psig. Thus, the range of the existing accumulator pressure transmitter is adequate to monitor any expected pressure within the accumulator.

Accumulator Tank Level The South Texas Project has installed Category 3 accumulator level instrumentation to monitor the status of the accumulator level primarily for technical specification surveillance. The span of the installed instrument is approximately 14 inches, from 59 to 64 percent of the tank volume. Technical Specification 3.5.1 requires that the accumulator volume is maintained between 11598 and 12023 ft3 during normal operation. The two series check valves in each accumulator discharge line prevent fluid addition during operation. Any malfunction of the two series check valves would be imediately indicated to the operator in the control room.

Accumulator isolation valve position, accumulator vent valve position, and accumulator pressure (all of which are Category 2 instrumentation) provide the operator adequate information to monitor the status of the accumulators.

Table 7.5-1 has been revised to reflect this information (see attached annotated pages).

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, . ATTACHMENT 4 ST-HL-AE- /030

__ PAGE F OF A0 INEL Report Exception:

6. Accumulator isolation valve position--the applicant should provide the information required by Section 6.2 of Supplement No. I to NUREG-0737 for this variable, identify any deviation and justify those deviations identified (Section 3.3.13).

Response

The South Texas Project accumulator isolation valve position meets the Regulatory Guide 1.97, Rev. 2 Category 2 requirements. Table 7.5-1 has been revised to reflect this information (see attached annotated pages).

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ATTACHMENT 4 ST-HL AE //,30 PAGE 9 OF Jo INEL Report Exception:

7. Reactor coolant pump status--the applicant should install the motor current instrumentation in accordance with Regulatory Guide 1.97 (Section 3.3.15).

Response

The Emergency Operating Procedures do not use the RCP motor current to assess the operational status of the reactor coolant pumps; the reactor coolant pump breaker positions are used. Therefore the reactor coolant pump breaker position has been classified as a Type D, Category 2 variable in Table 7.5-1.

Reactor coolant pump motor current is available in the control room via meters, one per pump. This current instrumentation conforms to Regulatory Guide 1.97, Rev. 2 requirements for Category 3 instrumentation.

Table 7.5-1 has been revised to reflect this information (see attached annotated pages).

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ATTACHMENT # ~ '

ST HL AE- /63o PAGE /00F Ao INEL Report Exception:

8. Pressurizer heater status--the applicant should provide the recommended instrumentation (Section 3.3.16).

Response

The-South Texas Project has 2 banks of pressurizer heaters normally loaded on the Class 1E emergency buses. Hence, the requirements stated in NUREG-0737,Section II.E.3.1 are met without requiring any operator action.

The above information together with pressurizer breaker position status indication (see Table 7.5-1) is adequate to determine proper heater energization.

Table 7.5-1 has been revised to reflect this information (see attached annotated pages).

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ATTACHMENT A l ST-HL-AE /430 PAGE llOFJO INEL Report Exception:

1 9. Quench tank level--the applicant should provide the information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable, identify any deviation and justify those deviations identified (Section 3.3.17).

l 10.. Quench tank temperature--the applicant should provide the information j required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this

, variable, identify any deviation and justify those deviations identified (Section 3.3.17).

11. Quench tank pressure--the applicant should provide the information

required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable, identify any deviation and justify those deviations identified (Section 3.3.17).

Response

Table 7.5-1 has been revised to reflect the requested information (see attached annotated pages).

The pressurizer relief tank (quench tank) temperature range (50 to 350*F) is adequate to monitor any expected conditions in the tank. For the design basis pressurizer steam discharge, the pressure relief tank (PRT) water temperature is maintained below 200'F. The Emergency Operating Procedures direct the operator to check if the PRT pressure and temperature are increasing to determine if there is an ongoing loss of RCS inventory v.ia Jeakage to the PRT. If a discharge results in a pressure that exceeds the ' rupture disc design pressure, the disc would rupture and pass the discharge through the tank to the containment. The rupture disc release pressure is 91 psig (corresponding saturation temperature is approximately 320*F). Following breach of the disc, the temperature of the tank will not exceed the saturation temperature associated with the existing containment pressure. The pressurizer relief tank pressure range is 0 to 100 psig.

The PRT is a 2100 cubic feet tank, lying horizontally with a length of 375.75 inches. The inside diameter of the PRT is 114 inches with the low level tap 7 inches up from the bottom and the high level tap 7 inches below the top of the tank.

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ATTACHMENT 4 ST-HL-AE- /G3o PAGE 11DF AO INEL Report Exception:

12. Containment atmosphere temperature--the applicant should provide the information required by Supplement No. 1 to Section 6.2 of NUREG-0737 for this variable (Section 3.3.18).

Response

Containment atmosphere temperature is not a key South Texas Project variable.

The key variables for monitoring the accomplishment of containment cooling are containment spray flow (D2), containment water level (wide range) (A1, 81, B2, C2, and D2), containment water level (narrow range) (Al, B2, C2, and D2),

containment pressure (A1, B2, C1, C2, D2), containment spray system valve status (D2), containment spray pumps status (02), and the RCB fan cooler differential pressure / status (D2). Innediately after containment spray is initiated, the containment atmosphere is saturated and the temperature is calculated from the containment pressure. Since the operator does not utilize this parameter to verify containment cooling, containment atmospheric temperature has been classified as a Category 3 parameter.

Table 7.5-1 has been revised to reflect this information (see attached annotated pages).

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• ATTACHMENT 4 ST HL AE /G30 PAGE l30F2j3 INEL Report Exception:

13. Containment sump water temperature--the applicant should provide the recommended instrumentation for this variable or identify other instrumentation that provides the same information (Section 3.3.19).

Response

Containment sump water temperature is not required for emergency core cooling system operation or assurance that minimum NPSH requirements are met. NPSH calculations conservatively assume saturated water is present (see FSAR Section 6.2.2.3.5). Containment water level measurements indicate that a source of water is available and, as described in Note i of Table 7.5-1, containment cooling is verified by other plant parameters. This variable designation is therefore Type D, Category 3. Should an indication of sump water temperature be desirable, the RHR heat exchanger inlet temperature should be used.

Table 7.5-1 has been revised to reflect this information (see attached annotated pages).

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. - ATTACHMENT A ST HL-AE /G20 PAGE P40F am INEL Report Exception:

14. High-level radioactive liquid tank level--the applicant should provide the information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable, identify any deviation and justify those deviations identified (Section 3.3.20).

Response

The liquid radwaste system is 'not required following an event. Level instrumentation has been provided for the various tanks in the Liquid Waste Processing System (as discussed in FSAR Section 11.2). Indication and alarm are provided in the radwaste control room, which is located in the Mechanical Auxiliary Building, except for the Reactor Coolant Drain Tank. Indication and alarm for the RCDT are provided in the control room.

Table 7.5-1 has been revised to reflect the requested information (see attached annotated pages).

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• ATTACHMENT 4 ST HL AE- Iro30 PAGE /3 OFJo INEL Report Exception:

15. Radioactive gas holdup tank pressure--the applicant should provide the information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable, identify any deviation and justify those deviations identified. (Section 3.3.20).

Response

The South Texas Project Gaseous Waste Processing System does not utilize gas holdup tanks. The GWPS design description has been provided in FSAR Section 11.3. This parameter is not applicable to the STP design.

Table 7.5-1 has been revised to reflect this information (see attached annotated pages).

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. . ATTACHMENT A ST HL AE /439 PAGE /6 OFa n INEL Report Exception:

16. Emergency ventilation damper position--the applicant should provide position indication for these dampers in accordance with the recommendations of Regulatory Guide 1.97 (Section 3.3.21).

Response

Ventilation dampers which are required to perform a safety function are provided with position indication instrumentation which meets the requirements of Regulatory Guide 1.97, Rev. 2 Category 2.

Table 7.5-1 has been revised to reflect this information (see attached annotated pages).

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ATTACHMENT 4

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• ST HL AE-/G30 PAGEI? 0FJ4>

INEL Report Exception: l

17. Vent from steam generator safety relief valves or atmospheric dump valves--the applicant should provide the information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable, identify any deviation and justify those deviations identified (Section 3.3.22).

Response

As indicated in NUREG-0737, Item II.F.1, offline monitors are not required for PWR secondary side main steam safety valve and dump valve discharge lines.

For this application, the externally mounted main steam line radiation monitors are provided, as indicated in FSAR Section 7A.II.F.1.

Table 7.5-1 has been revised to clarify how STP has met this requirement (see attached annotated pages).

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ATTACHMENT 4 ST-HL AE- tG30 PAGE Ia OF Ao INEL Report Exception:

18. Plant and environs radiation--the applicant should provide the range of the instrumentation provided for this variable, identify any deviation and justify those deviations identified (Section 3.3.24).

Response

Table 7.5-1 has been revised to provide the range of this instrumentation (see attached annotated pages).

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ATTACHMENT A ST.HL AE- /63o PAGE /4 OF.h3 INEL Report Exception:

19. Plant and environs radioactivity--the applicant should provide the information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable, identify any deviation and justify those deviations identified (Section 3.3.25).

Response

Table 7.5-1 has been revised to provide the information requested for this instrumentation (see attached annotated pages).

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ATTACHMENT A ST44L AE- / 6 PAGE ao 0F INEL Report Exception: ,

20. Wind direction--the applicant should provide the information required by Supplement No. 1 to NUREG-0737 for this variable, identify any deviation and justify those deviations identified (Section 3.3.26).

21. Wind speed--the applicant should provide the information required by Supplement No. I to NUREG-0737 for this variable, identify any deviation

'and justify those deviations identified (Section 3.3.26).

22. Estimation of atmospheric stability--the applicant should provide the information required by Supplement No. I to NUREG-0737 for this variable, identify any deviation and justify those deviation identified (Section 3.3.26).

Response

Table 7.5-1 has been revised to provide the information requested for this instrumentation (see attached annotated pages).

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ATTACHMENT B ST HL-AE Ib3 D PAGE l OF 225 Attachment B This attachment provides the Amendment 53 Table 7.5-1 (amendment in process) marked up with further changes required to respond to NRC letter dated February 24, 1986 and its attached INEL report.

The5e revisions to Table 7.5-1 will be incorporated in a future amendment of the FSAR. That amendment will also incorporate revisions required in Appendix 78 to correspond with Table 7.5-1.

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TABLE 7.5-1 POSY ACCIDENT MONITORING INSTRLMENTATION Sensor cuetification Control Implemen- Sensor EOC TSC Conformance Yype/ Environ- Number Room tetton Power Indice- Indica- to RG 1.97, Verlebte Rense/ Status Category mental Selsmic of Channels Indication Date Stply tion tion Rev. 2 RCS Pressure 0 3000 pelg A1,31,82, Yes Yes 1 ODPS Core Load 1E Yes Yes Note b (Wide Range) C1,C2,02 1 recorded RCS Wide Pange 0 NF A1,51,32 Yes Yes 1 per loop GDPS Core Load 1E Yes Yes Conforms Y 4 recorded E s Wide Range 0-7D(fF A1,51,92 Yes Yes 1 per loop CDPS Core Load 1E Yes Yes Conforms Y 4 recorded Wide Renee Steen 0 1001 of A1,51,52, Yes Yes 1 per steem OOPS Core Load 1E Yes Yes conforms Generator Weter span D2 generator 4 recor&d $3 un M Level H b '

b Norrow Renee Steam 0-100E A1,81,52, Yes Yes 4 per steen SDPS Core Load 1E Yes Yes Conforms N Generator Weter of open D2 generator 1 per SG $

Levet recorded Pressurizer Water 0 100E A1,51,02 Yes Yes 4 cDPS Core Load 1E Yes Yes Conforms Levet of span 1 recorded Contalement -5 to 65 pois A1,81,52 Yes Yes 4 eDPS Core Load IE Yes Yes Conforms , g,.y Pressure C1 C2,02 2 recorded ig@

Stecedine 9 1400 pelg A1,31,02 Yes Yes 3 per loop cDPS Core Loed 1E Yes Yes Confones W

' g1=E Pressure 1 per loop O

recorded '1, 2 Refueling Water 0-1001 A1,81,D2 Yes Yes 3 cDPS Core Load 1E Yes Fes Conforms h[

/

ig Storage Yank of span 2 meters

" (RUST) Water Level 2 recorded b

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YASLE 7.5-1 POSY-ACCIDENT leONit0 RING INStat M NTATION (Continued)

Sensor El. - #s* ountIfication Control Implemen- Seneer EOC TSC Conforimance N O' 4 Type / Erwiron- Nu 6er Room totion Power Indice- Indice- to RG 1.97, verlebte RenNe/ Status Category mentet Se_isyc of Chamels Indicotlon Date Syyty tion tion Rev. 2 contalrument Water 648%400-ge&a. A1,31,52 Yes Yes 3 GDPS Core Load 1E Yes Yes Conferine I'* al'c Levet (Wide Range) ;0['M 1 C2,02 1 recorded Mets sa Conteltment Water a.ee- ne

• A1,52,C2 Yes Yes 2 GDPS Core Load 1E Yes Yes Conferine Levet (Norrow ---*a P D2 2 recorded Le also Range) W Kl. - A6*f Jo Et.- se'9

• Aunillery Food- 0 1001 of A1,et,02 Yes Yes 3 GDPS Core Load 1E Yes Yes Conforma 53 unter Storage span 1 recorded Yest (AFST) Water Level

v. Aunttlery Feed- 0 700 gai,51n A1,81,02 Yes Yes 1 per loop cDPS Core Load 1E Yes Yes Note o 1

water Flow 4 meters 4 recorded Nigh Range A1,81,52, Yes Yes 2 CDPS Core Load 1E Yes Yes Note s 1Rpr to Contalrument 10 R/hr C2,E2 2 meters Radiation Level Caume 2 recorded Steen Generator 10' to 10 A1,52,C2 Yes Yes 1 per blow- CDPS Core Load 1E Yes Yes Conforms Bl

• Radle- MCl/cc down line 4 meters tion Levet 4 recorded > -4 H c)l m >a Steentine Redle- 10' to 10 A1,82,C2, Yes Yes 1 per steen QDPS Core Load 1E Yes Yes Conforms i,$

tion Levet E2 line 4 meters (s...I,, E:

pl/cc F cea e 4 recorded .u.,) %52 g _ va A sc . 9-b D O' Mr. $slief 9,,

v /4,t% )

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YABLE 7.5-1 POST ACCIDENY leONITORInc INSTRtM NTATION (Continued) 3 Sensor Quellfleetion Cor: trol laptemen- Sensor EOC TSC Conformance Type / Environ- Wimber Room tetton Power Indice- Indice- to RG 1.97, Verletzte Rense/ Status Category sentet Seismic of Channets Lndication Date Supply tion tion Rev. 2 Core Exit 100 2200 F A1,51 C1 Yes Yes 2 tralne of GDPS hottest Core Loed 1E Yes Yes Conforms Yeaperature 25 therno- thermocawte co gles each, and everage egJetty dis- of hottest tributed gJedront re-scross core corded (In gJed- 53 rents)

RCS St& cooling 200*F sth- A1,81 Yes Yes 2 CDPS Core Load 1E Yes Yes Conforme cooling to 2 recorded y

5fFstperheet y

• m u 3 1 Iseutron Flim 10 to 2001 31,02 Yes Yes 2 CDPS Core Load 1E Yes Yes Note r y u (Extended Range) Futt Power 2 recorded g Neutron Flum -0.5 to + .0 51,02 Yes Yes 2 00PS Core Load 1E Yes Yes Note r Stortty Rete @ recorded as neutron flum Reactor Vesset Upper Core 31,C2,02 Yes Yes 2 CDPS Core Load 1E Yes Yes Conforms Water Levet Sepport Plate 1 recorded togapofvesset

> -4 w Contelruent Isolation Velve OperVClosed C2,D2 Yes Yes 1 per vetve 1 pelr of lights per Core Load 1E Yes Yes liete e hb$

40 g@"

D Ctatus vetve 0-O,_.

.2 rnE H

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TABLE 7.5 1 POST ACCIDENT 90lITORING INSTRUMENTATION (Continued) t sensor ouellfleetion Control Implemen- Sensor EOC TSC Conformerce Type / Environ- Ihmber Room totim Power Indice- Indice- to RG 1.97, verlebte tense / Status Cateeory mentet Selsmic of Channete Indication Date Steply tion tion Rev. 2

$3 Containment 0-10E 31.C1 Yes Yes 2 ODPS Core Load 1E Yes Yes Conforme Nydrogen Concentration 1 recorded Corr:entration Controt stod Rode on 03 No No 1 per rod LED Core Load N-1E No No Conforms 40 Poeltlen Bottom (Note a)

Indication Contelnesnt 0-180 pelo C1,C2 Yes Yes 2 ODPS Core Load 1E Yes Yes Conforme Pressure 1 recorded (Extended Range)

U RCS Pressure 0 3500 pois A1,51,C1 Yes Yes 2 CDPS Core Load 1E Yes Yes Note b (Extended Range) 2 recorded 53 Prienry Coetent 4lg%

C4E3 No No 1 post CRT (ERrDADS) Core Load JegW Tes Yes Notes d, h -

Activity and N*I' occident #~ if Sempting soupling

• system Unit h uote a [ C2,E2 Yes No 1 CRT (R9tS) Core Load N-1E Yes Yes Conforms Radlett (Note,e, v) bh 6 -1 Oi-4 Fuel Nandtleg '10 to 10 C2,E2 Yes Yes 2 QDPS Core Load 1E Yes Yes Confonme M-$r Stdg. Exhaust A(Cl/cc 2 meters W Radletion Levet 2 recorded o,1 &;, m s

b SL)o D'

-4 2 u y i - RCS S,Lkle. 0- f*W p 63,E3 No do i (Ar (caposed b U NM [es Its 3 e.ua U

1 3

TABLE 7.5-1 POST ACCIDENT NONITORlWG INSTRUDENTAYl0N (Contirased)

Seneer euellfleetion Control It9temen- Sensor EOC YSC Conformance Type / Environ- Number Room totion Power Indice- Indice- to RG 1.97, Verletd o Range / Status Cateeory mental Selemic of Channels Indication Date Supply tion tion Rev. 2 Adjacent Building 10 to 10 C3 No No 5 CRT (RMS) Core Lead M 1E Yes Yes Note 1 53 Aree Radletion eR/hr Levet Site Erwiroruentet C3,E3 No No N/A Portable Core Load N-1E No No Conforms Redletten Levet to4 ,Sar//A/h;

/ Senpting Nok c.

(Portelde Monitoring)se**45,pp4%

N Preseurfter PORV Open/ Closed 32,02 Yes Yes 1 per velve 1 pelr of Core Load 1E Yes Yes Conforms Status lights per vetve w N

, Pressuriter PORV Open/ttooed D2 Yes Yes 1 per velve 1 pelr of Core Loed 1E Yes Yes Conforms 40 i

$ stock vetve Status tights per yl 4 vetve g Pressuriter Safety Open/ Closed 32,02 Yes Yes 1 per volve 1 Alarm Core Load M-1E Yes Yes Conforms Velve Status CRY (ERFDADS)

Pressurfter Hester Open/ Closed D2 Yes Yes 1 per bank 1 pelr of Core Load IE Yes Yes Note e greeker Poeltion lights per bank j Pressurizer 1790-2500 D2 Yes Yes 4 cDPS Core Load 1E Yes Yes Confenes hH Pressure pelg 1 rec W 53 g a

g

!  : ME E

o

- 5;le. s. :<. - ~ kl Nele.J c%a3 w. M,  % P.4 Uc cr. 61 N- sr n. n. C,4.~ ?W uwa t Nok ad ya

},  ? Pad.'onh)L=~4 Ss-f ; g

! g ( M W A l.n 9

TABLE 7.5-1 POST ACCIDENT MONITORING INSYNUMENTATION (CentInued)

Sensor Quellfleetion control Implemen- Sensor EOC TSC Conformance Type / Environ- Ntaber Room tetton Power Indice- Indice- to RG 1.97, Verlebte Rense/ Status Category mentet Seismic of Chamels Indication Date Steply tion tion Rev. 2 Yes 1,^ ? ? "

02 % No No 1 per b w per pe M Core Load N-1E Yes (Conforms ucP WA status)D  %/d*d P" 40 Ad.,. c d. 8- Ws D3 No A/o j, p., m 1,' 4.c p.c Qfe, y.ir Afo y, Pressuriner Sprey open/ Closed D2 No No 1 per vetve Yghtper Core Load N 1E Yes Yes Confonus Velve Status volve Charging Flow C 500 get/ min D2 Yes Yes 1 ODPS Core Load 1E Yes Yes Conforms Letdoun Flow 0 500 set / min D2 Yes Yes 1 1 meter Core Load M-1E Yes Yes Conforms volum controt 0 100E D2 Yes Yes 2 1 meter Core Load 1E Yes Yes Conforme y Tonk (VCY) Water of span -

1 oo Levet .

CVCS Velve Status Open/ Closed D2 Yes Isoletion 1 per vetve 1 pelr of Core Load 1E/N 1E Yes Yes Conforms 53 Velves tights per (Note f)

Only velve Charging Pu p On/off D2 Yes Yes 1 per ptmp 1 pelr of Core Lead 1E Yes Yes Conforms Status Lights per (Note f)

PWP mtD Boric Acid Transfer (MT)

OWOff D2 Yes Yes 1 per pump 1 pelr of tights per Core Load 1E Yes Yes Confonus (Note f)

[>[

rn r -

Pw p Status ptmp 9 Om RCP Seet 0 20 set / min D2 Yes Yes 1 per toop QDPS Core Load 1E Yes Yes Conforms b2 D Injection Flow 4 recorded (Note f) bo

$ YW N

\ 0

TABLE 7.5 1 POST-ACCIDENT WONITORING INSTWJIENTATION (Contirwed) 9 9ensor Quellfication Control Imptcoen- Sensor EOC TSC Conformance Type / Environ- Nusber Room tetton Power Indice- Indice- to RG 1.97, Verlebte Rense/ status Category mentet seismic olchemet s Indication Date Simply tion tion Rev. 2 SG Atmospheric 0 1001 Open D2,E2 Yes Yes 1 per valve GDPS Core Load 1E Yes Yes Conforms PORY Status 1 meter per valve Hein Stemotine Open/ Closed B2,02 Yes Yes 1 per volve 1 pelr of Core Load 1E Yes Yes Conforms Isoletion vetve lights per (Note f) 40 Statue valve IceIn Steendine open/ Closed 32,02 Yes Yes 1 per valve 1 pelr of Core Load 1E Yes Yes Confoms Bypees Valve lights per (Note f)

Status vetve SG Safety Velve open/ Closed D2,E2 Yes Yes 1 per volve Atorm Core Loed N-1E Yes Yes Conforms e

1 Status CRT (ERFDADS)

Isoln Fee &eter Open/ Closed D2 Yes Yes 1 per volve CRT (ERFDADS) Core Lead 1E Yes Yes Confe u Control Velve (Note f)

Status 53 Main Feethseter Open/ Closed D2 Yes Yes 1 per volve CRT (ERFDADS) Core Load 1E Yes Yes Conforms Contret Bypees (Note f) wy Velve Status [

m

[%. >

Nein Festater w tooed D2 Yes Yes 1 per vetve 1 pelr of Complete 1E Yes Yes Confonos g> ~r footetton Vetge lights per (Sote f) o kto Status valve N2tm --i D D 5

a, i

l

TABLE 7.5 1 POST ACCIDENT MONITORING INSTRLDIENTATION (Continued) f Sensor Quellfication control Implemen- Sensor EOC TSC Conformance Type / Environ- Ntaber Room tetton Power Indice- Indice- to RG 1.97, Verlebte Range /Statw Category mentet Seismic of Chereiets Indication Date Sgely tion tion Rev. 2 Mein Feeduster Open/ttooed D2 Yes Yes 1 per velve 1 pelr of Complete 1E Yes Yes Conforms Isotation tights per (Note f)

Bypese vetwe vatwe Status 6 53 Main Foodseter 0 5.0 x 10 D2 Yes Yes 3 per loop GDPS Core Load IE Yes Yes Conforms Ftou tbe/hr 1 per toop recorded SG 5toudoun tipan/ Closed 02 fes Yes 1 per volve 1 pelr of Complete 1E Yes Yes Conforme Isolation Velve lights per (Note f) m H

U Status valve "

• 40 l>

o SG Stoudoun Open/ Closed D2 Yes Yes 1 per velve 1 polr of Ceeplete 1E Yes Yes Conforms y Lights per (Note f) W Sample Isolation valve Status vetve IIMSI Flou O 2000 set / min 02 Yes Yes 2 per SI 6 meters Core Load N-1E Tes Yes Conforms

.- pump (hot tog, cold teg) 53 LMSI Flou 0-3500 set / min 02 Yes Yes 2 per $1 6 meters core Load N 1E Yes Yes Conforms N (hot leg) Immy (hot  ;

g o

8 5000 set / min (cold teg) teg, cold tes) g

Os

~

l b O1 N G

TABLE 7.5-1 POST ACCIDENT MONIt0RI_NG_INSTRUMEutAT104 (Continued)

Sensor Quellfleetion Control laptemen- Sensor EOC TSC Conformance Type / Environ. Ihaber Room totion Power Indice- Indice- to RG 1.97, Verlebte Ranse/ Status Category mentet Selsmic of Channets Indication Date Steply tion tion Rev. 2 3 Atele.a,b ECCS Accuiutator 0 700 pelg 02 Yes Yes 2 per tank # meters, on Core Load N-1E Yes Yes eeneesmo.

Pressure .

F 8 a J....la 4

Ausitlery Feed- Open/ Closed D2 Yes Yes 1 per vetve 1 pelr of Core Load 1E Yes Yes Conforms water Velve Status lights per (Note f) vetve Contelnment Sprey 0- D2 Yes Yes 1 per train 3 meters Complete N 1E Yes Yes Conforms 40 Flow Mm contelnment Sprey open/ Closed D2 Yes Yes 1 per vetve 1 pelr of Couplete 1E . Yes Yes Conforms y System Velve lights per (Note f) y velve *d y Status b tn

~ contelrunent Spray On/off D2 Yes Yes 1 per pump 1 pelr of Complete 1E Yes Yes Conforms y Pssp Status tights per (Note f) pump Reector Contelnment 3 4 in. water D2 Yes Yes 1 per fan 1 stern per Core Load 1E/N 1E Yes Yes Note a Fan Cooter Dlffer- gege On/Off fan y

entlet Pressure /

Status 53 CCW Pump Discharge 9-150 pois D2 Yes Yes 1 per train ODPS Core Lee '_ Yes Yes Confocus gj Pressure (Note f) p[3>$

rn g Contelnment Vent- Open/ Closed 02 Yes Yes 1 per vetve 1 pelr of Core Load 1E Yes Yes Conforms N izh itetton Velve lights per  %

y Status valve '15 2 e  %%d

^ >

• E ,ces u .u u,w o,q a,,a a r., u, i s iec./ u..a .w m u, w e niu <-

v. tee, sa .- n - --

l

TABLE 7.5 1 PO.f ACCIDENT NONITORING INSTRUMENTATION (Continued) t sensor ouellfication Control Implemen- Sensor EOC YSC , Conformance Type / Environ- Number Room tetton Power Indice- Indice- to RG 1.97, Verlebte Range / Status Category mentet Selsmic of Chamels Indication Date Supply tion tion Rev. 2 CCW needer 50 250*F D2 Yes Yes 1 per train ODPS Core Load 1E Yes Yes Conforms Temperature CCW Surge Yank 0-1005 of D2 Yes Yes 1 per tank QDPS Core Load 1E Yes Yes Conforms Water Levet open coupertment (Note f)

W cetJ Core Load 1E 53 CCW Fleet to ESF 0 eppropriate D2 Yes Yes 1pery GDPS Yes Yes Conforme Components l get/ min for y D.n.A <y caponents? __y 2o0009.f/ c.n SF RC WC, o-ttooyJ,f ;s t 894 H Y o-5poo9 4/ %

-J CCW Velve Status Open/ Closed D2 Yes Yes 1 per volve 1 pelr of Core Loed 1E Yes Yes conforms tights per (Note f) y volve

- Y 1 per mejor cDPS Core Loed 1E Yes Yes Conforms ECW Flow to ESF fD sppropriatel D2 Yes Yes Components get/ min cego- ESF component .

(Note f) inent/heede jr Open/ Closed D2 Yes Yes 1 per valve 1 pelr of Complete 1E/N-1E Yes Yes Conforms ECW Vetve Status tights per (Note f) vetve or meter U(n >

> -4

> ESF Emironment Temperature D2 Yes Yes 1 per ESF f etern Core Load N 1E Tes Yes Conforms Y Yesperature above setpoint component / (Note f) 40 iS o- cublete MK s Om

$ i

% cctJ P y <=l.c o-sop /:a y0,k sa ces.> v o-no,eco yt ],.g 56 ag D4 o-noo 4;,

l Esiukd cW b4 o- f.oo y1/ ;.

o. isoo pi/, .w

YAOLE 7.5 1 POST ACCIDENT IIONITORING INSTRUMENTAfl0N (Continued)

Sensor Quellfleetion control Implemen- Sensor EOC TSC Conformance Type / Environ- Ntaber Room totion Power Indice- Indice- to RG 1.97, Verlebte tense / Status Category mentet Seismic of Charmets Indication Date Supply tion tion Rev. 2 ESF Cthicle Fan Stopped / D2 Yes Yes N

1 per E654 1 pelr of Core Load IE Yes Yes conforms Fen /Cooter Rtsining

^

,,lef -iP- ; _ !c. tights per (Note f) 53 Status eM ltem StentByr Power sus Specific D2 Yes Yes 1 per but 1 meter or Core Load 1E/N 1E Yes Yes Cadores and Emergency eterm for Power Source each power Status source Other Safety- Component D2 Yes Yes 1 per source 1 meter or Core Load 1E/N 1E Yes Yes Conforms 40 Reteted Enerfy Specific storm for (Note y) y Sources each power y tn source

~ m RINt IIsot Enchanger 5040[F D2 Yes Yes 1 per heet ODM Core Load 1E Yes Yes Conforms N Discherge exchanger 3 recorded Temperature Rtut Flow 0-4000 set / min D2 Yes Yes 1 per train GDPS Core Load 1E Yes Yes Conforms 3 meters Open/ Closed D2 Yes Yes 1 per vetve 1 pelr of Core Load 1E Yes Yes Conforms 53 RNR Velve Status tights per (Note f) Kg Reector Yrlo open/ttooed D2 Yes Yes 1 per breake ,1 pelr Complete 1E Yes Yes Conforms ereeker Position of lights (Note f) 40 n s@

[ per break g O CA S

u, 14

TABLE 7.5-1

, POST-ACCIDENT MONITONING INSTNUMENTATION (Continued) f Sensor Quellfleetion Control I ntemen- Sensor EOC TSC Conformance Type / Environ- Ihauber Room totion Power Indice- Indice- to RG 1.97, Verlebte Ranse/ Status Categoy e tet Setsmic of Channels Indication Date Supply tion tion Rev. 2 Yurbine governor open/ Closed D2 Yes No 1 per volve 1 pelr of complete N 1E Yes Yes Conforms Vetve Position tights per (Notes f,z) vetve 40 Yurbine stop open/ Closed D2 Yes No 1 per volve 1 pelr of Complete N-1E Yes Yes Confones Vetve Position tights per (Notes f,z) vetve Motor-Driven On/Off D2 Yes Yes 1 per ptmp 1 pelr of Core Load 1E Yes Yes Conforms Aumittery Feed- tights per (Note f) water Ptap Status puup 4 g H Aunillery Feed- 0-5000pois, 02 Yes Yes 1 pump dis- eDPS,1 meter, Core Load 1E Yes Yes Conforms hN water Turbine Open/ Closed charge 1 pelr of (Note f)

Ptap Status pressure in lights per 53 $

xs dicator, 1 vetve per steem in-tot valve St Ptap Status Orvoff D2 Yes Yes 1 per pump 1 pelt of Complete 1E Yes Yes Conforms lights per (Note f) pts, 40 g>

ag-1 SI vetve Status Open/ Closed 02 Yes Yes 1 per volve 1 pelr of complete 1E Yes Yes conforms TN 4

Lights per (Note f) $

g vetye p tv-

-- (p CF 8 g my J. Q ;-(* k % p. 7s-2T) i 5

TAOLE 7.5-1 POST ACCIDENT HOCITORING INSTRtMENTAfl04 (Continued)

Sensor Quellfleetion Control laptemen. Sensor EOC TSC Conformance Yype/ Environ- Nusber Room totion Power Indice- IMice- to RG 1.97, Verlebte Range / Status Category mentet Selsmic of themets Indication Date Supply tion tion Rev. 2 Essentist Cooling On/off D2 Yes Yes 1 per pump 1 pelr of Complete 1E Yes Yes Confonus Water Pulp Status tights per (Note f)

PWp CCW Puup Statue On/Off D2 Yes Yes 1 per pump 1 pelr of Complete 1E Yes Yes Confonus tights per (Note f) 40 puip RNR Pulp Status On/Off 02 Yes Yes 1 per po p 1 polr of Complete 1E Yes Yes Confonus lights per (Note f) u

" C vi SI Actuation On/Off 02 Yes Yes 1 per actus- 1 Aterm Core Load 1E Yes Yes Conforms b Status tion train u h

Contelrument loo- On/Off D2 Yes Yes 1 per actue- 1 Alarm Core Load 1E Yes Yes Conforms totion Actuation tion trein Status 53 Control Room 10 to E3 No No 1 CRT (ans) Core Load N-1E Yes Yes Note t Redletion Level 10 se/hr (area) 10 to 10 E2 Yes Yes 2 GPDS Core Loed 1E Yes Yes Conforms hM g

/fcl/cc(Intake alr) 2 meters 2 recorded hi$

s e

NE O~ m U

" M2 g --4 a w

TABLE 7.5-1 <

POST ACCIDENT MONITORING INSTRUMENTATION (Continued) i Sensor OuotIfIeatIon Controt Isptemen- Sensor EOC TSC Confornance Type / Environ- Nusber Room tation Power Indice- Indice- to RG 1.97, Verlebte Range / Status Category mental Seismic of Channels Indication Date Steply tion tion Rev. 2

-1 Access Aree 10 to E3 Yes No 1 per CRT (RMS) Core Load N 1E Yes Yes Note t 4

Redletion 10 R/hr designated 40 area Condenser Vacuun 10 to E3 Yes No 1 CRT (RMS) Core Load N-1E Yes Yes Note n Puup Radletion 10 Cl/cc Levet concentration from Liquid Pathways Liquid Re& este 10' to E2 Yes No 1 per plant CRT (RMS) Core Loed N-1E Yes Yes Note t y

10 y Cl/cc w

e Effluent Peth Flow Rete / Statue 191d RestseetB 0100E E3 No No 1 CRT (RMS) Core Load N-1E Yes Yes Note q of span Vetve Status Open/ Closed E2 Yes No 1 per vetve 1 pelr of Core Load M 1E Yes Yes Notes q, w lights per Kg v= ' ~ M&s Note v

%e Uhlt W M E2 Yes No 1 CRT (ERFDADS) Core Loed N-1E Yes Yes LA rnk

" n $

^

10" ,

. v.ac - Pp ~w g- n,a

$5 0 -

Uesk Omd% 0-540'

• IJied 6 M O ,5D fL (80-) TAgtE 7.5-1 ,

s.soo pk 46) ,

, g- POST ACCIDENT MONITORING INSTRUNENTATION (Continued) 4 AT -$ b 'T ,

Sp es Me. 0- 60*

~~

I.

ouellfication Control laptemen- Sensor EOC TSC Conformance Type / Environ- Nuuter Room tetton Power Indice- Indice- to RG 1.97, Verletde Rense/ Status Category mentet seismic of Channele Indication Date Steply tion tion Rev. 2

" * * **** I**1 8 CRT C Plad #8 Ne e eso scf Core Load M 1E Vee Veo Note v l_-_^ 0- E3 No No 1 GN4-44NeS4 4 r _-_ = = -

m ra~)

Pump Status On/Off E2 Yes No 1 per ptmp CRT (ERFDADS) Core Load N-1E Yes Yes Notes V, u 53 meteoretogical C- -

• M- E3 No No 15 CRT (ERFDADS) Core Loed N 1E Yes Yes Note u, L Permetters 0. 5 ""* -

N Contelnesnt Simp N/A E3 No No 1 poet CRT (ERFDADS) Core Loed N 1E Yes Yes Notes d, h and Atmospheric accident y SouptIng semptIng y

'o !

L system i O 5:

M gerlc Acid Tank --- --- - -- - - ---- ---- - -- - ...

Note s y' Charging Flow

" # # # # 40 Containment atmospherte F8-888*# " "* #* [ *" P AI -lK" No No Note 1 Teeperature e

> w #

r $cundeter # d d d d' --- d J # -- *- Note J Tank Levet h~

D3 * #* ,3 ." Q N sk e,.o;m a ekenesis I* 5 Yes ncpy

> ~4 -4 t-I, containment # # # # # # d M gete k r-sa-4ao*F D3 Ne No A rar l N-iK- Yes )h.s

Susp unter pa. H z cK7 (dittswos) Gr-f e/*- pm@g

4 E w Temperature i,, g t. Om U m z D3 M 1 "* ' ~

. LeJTM m3M ( #8b * *) h CA D  % M U QweL %4. o-s oopig D3 Na Na $ l ~slW &lsk N-S C W. M, Glrr s (Nole. e c) g, i

Aa J.Td r p3 No A/o i M %W "- M Ne #e GL

@M ,7

. ,y,,.g

~ (a.k .e)

i TABLE 7.5 1

• POST ACCIDENT MONITORING INSTRUNENTAfl0N (Continued) f Sennor htification Control Implemen- Sensor EOC TSC Conformance Type / Environ- thmber Room totion Power Indlce- Indice- to RG 1.97, Verlebte Ranse/ Status Category mental Seismic of Chamels Indication Date s y ty_. tion tion Rev. 2 Heat Removal by ~~ "" -- - -- "" -" "- -"- -~- ""

Note a the Contaltunent Fan Meet Removal System

$3

• ,& &,,7" J j ] ] 2 2 "

J J v--

lys./ Clod _ -

9A fe.s 1.s L r*e d %Inu w L"'

"j,f, ventitetton Q L leg &uifee fas %s g

I p4 Desper Poeltlen M R.Lo.Xas Ufl 0 -100'4 D3 No a L p.< u,.e 4g p. y n n ag s

.g-gy &sm M %4s aQ p t,, "

e m

M R>Le. c 4 G.<> - - - - - - - - - - - - - - - - - - - - ---

-- Aq a.p g; gu - - _

Pe .

o v> >

D -I-j Q

m .O>

%>I h, E n Osm 40 aa 4,shes/ e M lab h a u n -9,n x a e a y 44 . rue, e-m wra %

rt.a, M t ~vd % tu. rm . . , it.co.m c ,

yoI Q T J f< -

.,:n L Ad.o. % M -

w -u A.1- m ~

a . . n fG AMn . _

ATTACHMENT B

• ST HL-AE-/63o STP FSAR PAGE lgOFA:$

TABLE 7.5-1 (Continued)

NOTES i

l

a. Noble Gas: 10 e to los pCi/ce, Particulate: 10'11 to 108 pCi/ce, l i

Halogens: 10'11 to 102 pCi/cc.

To cover the required range of particulates and halogens, a combination of on-line detection and grab sample capability with onsite analysis is em-

- ployed. These monitors are environmentally qualified, but not seismically qualified, since they are attached to a non-seismic system. 40

b. RCS Pressure - one qualified channel of wide range RCS pressure and two qualified channels of extended range RCS press'are are used to monitor RCS pressure for STP.

c.

Containment Isolation Valve Status - STP has identified instrumentation that is necessary to assess the process of accomplishing or maintaining critical safety functions. The critical safety functions defined are equivalent to those utilized in the Westinghouse Owners Group Emergency Response Guidelines, i.e., Suberiticality, RCS Integrity, Reactor Coolant Inventory, Reactor Core Cooling, Heat Sink Maintenance, and Containment 53 Environment. Containment isolation valve status is not a critical safety function. However, the containment isolation valve positions were designated variables for monitoring the actual gross breach of the Ag,# containment and are thereforegqualifi"2 ak .c6 Category 2. criteria.

t-4 3 b

d. The STP Post-Accident Sampling System is sufficient for obtaining samples to perform detailed analysis af RCS coolant, containment sump, and con-

. ,A tainment 3atmospheric Category variables. Th activity.

rus ;sOfflinemeasurementsystemsareconsidered 4.sua.d sa 5', C 1.3 .

40 6

e.7Pless9tizerHeatfrStatus RG 1.97, ev. 2 specified that heater current l was A.1e4 prefejr 6d paramet for dete ining h ter status For STP, A

heater breaker positioti as selec for de raining pr surizer h ter I

Aftatus du 'to hardwa e considerations. enker posi on provid adequate h.u-y gg indicati to the o rator to/ ensure thdt the two p essurizer heater banks yovered from the Class lE busses are operable. J

f. The study performed on STP indicated that these parameters were needed in 53 the minimum set of parameters necessary to monitor the performance of:

1. Plant safety systems employed for mitigating the consequences of an accident and subsequent plant recovery to attain a safe st.etdown condition, including verification of the automatic actuation of safety systems.

40

2. Systems normally employed for attaining a cold shutdown condition.

g. Boric Acid Tank Charging Flow - For monitoring the performance of the Emergency Core Cooling System (ECCS), STP has designated Refueling Water Storage Tank (RWST) Invel, High Head Safety Injection (HHSI) Flow, 7.5-29 Amendment 53

. . ATTACHMENT 8

• STP FSAR ST HL AE- /63o PAGE /q OF ;;L3 TABLE 7.5-1 (Continued)

NOTES Low Head Safety (IllSI) Injection Flow, Containment Water Invel, and ECCS Valve Status. Since the ECCS does not take suction from the Boric Acid 40 Tank (BAT), the Boric Acid Charging Flow was not designated a key vari-able. If the operator uses the BAT for boration following an accident, normal charging flow and RCS sampling is used to demonstrate that the RCS is being borated.

h. Data entry is via manual keyboard.

i. (don i t Atmos eric opera - The WOG Emeygency Res onse Guide-es G) do t req re th paratoJ/to takeAin action at wou result Vg na rse consequence's if th Contsifusent temperature icatio was /

g(

q 53 pro ding an' erroneous vaJu'e. As niuch, tly'Containnynt tempe ture ,indi-cation is/ considered a D3 parame/er t and is not specifically identified on

<thie 1tstina.

j . ( Ac ' tor pres ~ re Analc t.a.. -mi valv ositi indic tion f r the tgdis

,f9q rge is tioty4alves acc ato nt v es ovide Ladequate status of the accumulators.

une#

k.[ Con inne e sumpjwater temperat e in cation is not u ilized by the op rato to talad cor etive a on. ther rameter ere des p tedj s g uD'SP e D vpfiabl to de stra that e Safe njectiogSystep (SIS) g( QsoperatingproprlywhentakingsuctionfromtheContainmentsus@.

1. Conforms to RG 1.97, Rev. 3. 40

m. Heat removal by the Containment Heat Removal System (CHRS) - Other para-meters were designated as STP type D variables to demonstrate that the containment heat removal systems are operating properly. These include the following:

o Containment Spray Flow e Containment Spray System (CSS) valve status e Containment Pressure e Containment Water IAvel e Containment Spray Pump Status e Reactor Containment Fan Cooler (RCFC) Differential Pressure e RCFC Status

n. Condenser Vacuum Pump Radiation Monitor - This parameter is considered to be a backup variable for the measurement of secondary side radiation.

7.5-30 Amendment 53

• '

• ATTACHMENT B ST HL AE-163o STP FSAR PAGE .2o OF e TABLE 7.5-1 (Continued)

NOTES Main steamline radiation monitors are adequate to provide primary indica-tion of this information. The condenser vacuum pump radiation monitor is environmentally qualified, but not seismically qualified, since it is 40 attached to a non-seismic system.

o'. The STP design utilizes four physically separate auxiliary feedwater lines. The four Class lE transmitters provide the redundancy required. l The requirement is to ensure flow to at least one intact steam generator post-accident. The required redundancy with a four loop plant is provided by one channel per loop. SG Water Invel Vide Range provides a diverse i backup Total AW flow (0-2800 gpm) is also displayed via the QDPS. 53 D.l .hd. .

p. ITm Eg~ency Ventilation Damper Position - As an alternate to monitoring 40 ventil tion damper position, STP apnitors radiogas, radioparticulate, and/o radioiodi concentratio at various locat ns in the plant which 53 proy de informa on concerning e status of the entilation system.

se paramet s include:

e Area diation in lo tions which con n, or could c tain, sig- p nifi ant quantitie of radioactive terial e U t vent radi as concentratio

/

)

e Radiogas co entration disc rged from non- adered vents i e Environs adiation 40 e

Fuelhandlingbuildingventradiatiop (o Effluent path flow rate '

q. Effluent Path Flow Rate / Status - Variables which provide the operator with information to estimate the magnitude of release of radioactive materials through identified pathways. Valve status is the primary variable and flow rate is a backup variable.

r. Neutron Flux - No diverse variable is required since *t.. fail m of one channel will not cause the operator to violate ene required safety fen- i ction.

I

s. Two Containment hi gh range monitors meet the requirements of a Type A variable. These monitors are Class 1E, redundant and fully qualified to Category 1 requirements. Six area monitors are located throughout Containment with the range of 0.1 to 10,000 mR/hr that provide additional monitoring over this range. In addition, the off-scale high readings of i the low range monitors provide some information to resolve ambiguity above this range. These two qualified high range radiation monitors also satis-fy the requirements of NUREC-0737.

i 7.5-31 Amendment 53 l _ _ _ ._ - - _

ATTACHMENT B

. e o ST-HL AE- /630 STP FSAR PAGE .110F Jt3 TABLE 7.5-1 (Continued)

NOTES

t. The study performed on STP indicated that these parameters were included in the minimum set of parameters necessary to monitor for release of radioactivity via liquid effluent pathways. These monitors are environ-mentally qualified, but not seismically qualified since they are attached to non-seismically qualified systems.

u'. Meets requirements of RG 1.23. #e[v /* 'Qf4 J.3-23 f.v *=M M I"d A -

v. For the purpose of radiological release calculations, the conservative assumption of maximum flow will be utilized. Actual flow Indication serves as a backup parameter and is designated Category 3.

i v. These Category 2 sensors are environmentally, but not seismically qual-ified, since they are attached to a non-seismic system.

x. Rod position indication is provided in the CR via the digital rod position indication system light emitting diode (LED) display.

y. Instrument loops on Class 1E systems are qualified up to and including channel isolation devices.

z. These Category 2 sensors are environmentally and seismically qualified; however, they are installed in a non-seismic system and are therefore not listed as seismically qualified instruments. They are installed using mountings similar to those used for comparable seismically qualified equipment, A

a.a. . d**** 4r :** el N % E .-* f w.4+< laa/ i .aru.ed d<.sp is mvN k Arts.kn 7A,i k E .F.1.

a.b .

a.Lj w g a., c . Ah k W Sl f 'Ad 'b#-

.d. A y M4 Us m MJ asf sw is pnvldd.

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Amendment 53  !

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ATTACHMENT B

. .. . AE- Ifo30 ST.HL4AOF PAGE .2_R Insert A: The appurtenances and power supplies for the containment isolation valves meet the intent of Regulatory Guide 1.97 Category 1 instrumentation. For isolation valves in series, a single indication on each valve is sufficient to satisfy the requirements 1 when those indications are powered from different trains. I Insert B: The maximum pressure allowed by the Technical Specifications is i

_ between 586 and 679 psig. The two series check valves in each i accumulator discharge line prevent fluid addition to the tank during operation. The accumulator discharge valves are also locked I open during operation. Hence, any malfunction of the two check

, valves would be imediately indicated in the control room. The accumulator is also protected by a spring loaded safety valve with a setting of 10 psig.

Insert C: The South Texas Project has 2 banks of pressurizer heaters normally loaded on the Class lE emergency buses. Hence, the requirements ,

stated in NUREG-0737,Section II.E.3.1 are met without necessitating operator action. Since the heater banks are normally loaded on emergency buses, heater breaker position was selected for determining pressurizer heater status.

Insert 0: The span of the installed instrument is approximately 14 inches from 39 to 64 percent of the tank volume. The two series check valves in each accumulator discharge line prevent fluid addition during operation. Accumulator isolation valve position, vent valve position and pressure (all of which are Category 2 instrumentation) provide the operator adequate information to monitor the status of the accumulators.

Insert E: The key South Texas Project variables for monitoring the accomplishment of containment cooling are containment spray flow, containment water level (wide range), containment water level (narrow range), containment pressure, containment spray system valve status, containment spray pumps status and RCB fan cooler differential pressure / status. Immediately after containment spray is initiated, the containment atmosphere is saturated and the temperature is calculated from the containment pressure. ,

l' Insert F: Containment sump water temperature is not required for emergency core cooling system operation or assurance that minimum NPSH requirements are met. NPSH calculations conservatively assume

saturated water is present (see Section 6.2.2.3.5). Containment 4

water level measurements indicate that a source of water is available and as described in Note 1, containment cooling is verified by other plant parameters. Therefore this variable

designation is Type D, Category 3. Should an indication of sump water temperature be desirable, the RHR heat exchanger inlet  !

temperature should be used. )

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1550g/0040g l

ATTACHMENT S ST HL-AE- /630 PAGE ;(3 0F cR3 Insert G: The offline measurements available and the corresponding ranges are as shown below:

Boron 0-6000 ppm pH 0-14 -

Specific Conductivity 0-1000 mhos/cm Dissolved Oxygen 0-20 ppm Chloride 0-20 ppm Dissolved Hydrogen 0-2000 cc/kg Gross Activity 10 Ci/ml - 10 C1/ml Gamma Spectrum 0-2000 mR/sec (uncorrected)

(determined by Ortek gamma spectroscopy system)

Refer to Appendix 7A, item II.B.3 for additional information.

Insert H: Indication and alarm for LWPS tank levels are provided in the radwaste control room, which is located in the Mechanical Auxiliary Building, except for the Reactor Coolant Drain Tank. Level indication and alarms for the RCDT are provided in the control room. For further information, refer to Section 11.2 and Table 11.2-5A.

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ATTACHMENT C ST.HL.AE 1630

,PAGE / OFJL.

Attachment C Amendnent 53 revisions of Table 7.5-1 were made to address the latest design relative to:

_1. Range clarification / verification

2. Number of channels verification

3. Displays verification

4. Reflection of plant effluent points

5. Wording clarification Letters sent to NRC providing information pertinent to this submittal include the following:

ST-HL-AE-1526, dated 11/22/85 Table 12.5.1 ST-HL-AE-1388, dated 10/14/85 Section 7A.II.B.3 Attached is a markup change in FSAR Section 7A.II.F.1 to show the revised sensor locations for the containment water level narrow range and wide range sensors. This information is referenced in Note aa to Table 7.5-1.

15499/00409

ATTACHMENT C.

ST-HL AE- th30 STP FSAR PAGE gEOF L Appendix 7A II.F.1 (Continued)

The plant effluent sampling system and analysis capability are further discussed in Section 11.5,-(12t::; . L 40 (3) Containment High Range Radiation Monitor Redundant Class monitors are provided in the Containment Building,180*

apsrt on thg operating deck (elevation 68*). The range of the monitors is 1R/hr to 10 R/hr gamma. l44 (4) Containment Pressure 40 Redundant Class lE containment pressure and extended range containment pres-sure monitoring channels provide continuous monitoring and recording of con-tainment pressure. These monitors cover a range of -5 to 180 psig; accuracj of these monitors is approximately 13 percent. 49 (5) Containment Water Level dos l The STP design includes redundant, Class /lE, wide range level mogitors. These monitors are located the containment floor elevation -11'3"Jas shown in Figure 7A.II.F.1-1. "'h vid: ::n;+ ~ 4 rar4 = ab----1: pr:cid; iIndi:: tier -

- nging fren th ::nte.i= n fhcr :: nn elevrtien ::::::p:nding :: : reter -

5 . ;1=: f 500,00^ g:ll:n:. In addition, Class 6 narrow range monitors are 40 provided in the normal and secendary sumps. S.: n:rrer ::ng: ;nitering ch:r <--

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These level monitors detect the presence of water at discrete predetermined levels. The accuracy of detection at each point is approximately 11/4 inch.

( lo.aed ~ A p. A The wide range monitors position the detectionIpoints more closely at the bottom than at the top. In addition, the dete tion points of the three moni-l

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tors are chosen to provide overlap. Above the at El. -W3", for the I first foot, detection points are one inch apart (i.e., four points per moni-tor, 3 inches apart). For the next two feet, detection points are three inches apart. For the next 3 1/2 feet, detection points are six inches apart.

49 The narrow range monitors provided in the normal sump (bottom at El. -17'3")

and the secondary sump (bottom at El. -12'3") use a detection point spacing of gw six inchest The normal sump monitor provides level detection between El.

I - 7'0" and -ll'D; the secondary sump monitor provides level detection at I

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