ML20203C853

Forwards Response to Eg&G Idaho Review of post-accident Monitoring Instrumentation Discussed in 860519 Ltr. Attachment 2 Identifies Reg Guide 1.97 Items Being Upgraded from Category 3,per 10CFR50.49

ML20203C853
Person / Time
Site:	Fort Saint Vrain
Issue date:	07/14/1986
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Berkow H Office of Nuclear Reactor Regulation
References
RTR-REGGD-01.097, RTR-REGGD-1.097 P-86460, TAC-51092, NUDOCS 8607210088
Download: ML20203C853 (17)

Text

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hPublic Service ~

2420 W. 26th Avenue, Suite 100D, Denver, Colorado 80211 g;;,$; m ,.

July 14, 1986 Fort St. Vrain Unit No. 1 P-86460 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Mr. H.N. Berkow, Director Standardization and Special Projects Directorate Docket No. 50-267

SUBJECT:

Emergency Response Capabilities Regulatory Guide 1.97

REFERENCES:

1) PSC Letter Warembourg to Johnson, dated February 28, 1985 (P-85065)

2) NRC Letter Heitner to Walker, dated March 12, 1986 (G-86134)

3) PSC Letter Warembourg to Berkow dated May 19, 1986 (P-86378)

4) PSC Letter Warembourg  !

to Berkow dated 1 June 20, 1986 (P-86435) l

Dear Mr. Berkow:

Reference 1 provided the NRC with Public Service Company's report regarding Regulatory Guide 1.97 (RG 1.97) Instrumentation. Reference 2 identified several open items in an interim report prepared by EG&G 7

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P-86460 ,

Page 2 July 14, 1986 Idaho Inc. Due to the integral relationship between RG 1.97 Instrumentation and 10 CFR 50.49 Environmental Qualification (EQ) of Electrical Equipment, the response to these open items has been delayed as indicated in Reference 3 and are provided herein in Attachment 1. The RG 1.97 items that are being upgraded from Category 3 are identified in Attachment 2. The upgraded items are a result of EG&G's comments as well as a review of the High Energy Line Break (HELB) accident in reference to 10CFR50.49. Notes to the table in Attachment 2 identify all the fields and further explains the level of qualification required for each specified accident scenario for the required RG 1.97 items.

As discussed in Reference 4, any RG 1.97 instrumentation upgrade that affects the FSV Master Equipment List (MEL) shall be incorporated into the FSV EQ Program and shall be added to the MEL as it is installed or upgraded per the Fort St. Vrain RG 1.97 implementation schedule (no later than start-up following the fourth refueling).

1 If you have any questions, please' contact Mr. M.H. Holmes at (303) 480-6960.

Very truly yours,

, b W Wuv 2

D.W. Warembourg, Mana r Nuclear Engineering Division DWW/KD:pa Attachments a

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Attachment 1 to P-86460 PSC RESPONSE TO EG&G IDAHO, INC.'S PAMI QUESTIONS The following are the responses and the explanations for the exceptions contained in EG&G Idaho, Inc.'s review of PSC's Post Accident Monitoring Instrumentation (PAMI) listing for the Fort St.

Vrain Nuclear Generating Station.

This report is formatted to respond on an item-by-item basis to the thirteen (13) exceptions listed in the " CONCLUSIONS" section of EG&G's report (Section 4, Pages 10 and 11).

1. Exception:

Final fission product cleanup system - the licensee should identify the key variable for this instrument group and upgrade the instrumentation for this variable to Category 1 (Section 3.3.2)

Response

Type C variables are those variables that provide information to indicate the potential for being breached or the actual breach of the barriers to fission product release. For light water reactors, these variables are:

(1) fuel cladding; (2) primary coolant pressure boundary, and; (3) containment. The variables at Fort St. Vrain which compare to these three light water reactor variables are:

(1) fuel particle coating . integrity; (2) liner and primary closure integrity, and; (3) PCRV concrete and secondsry closure integrity. The key parameters for these three Fort St. Vrain variables have been identified as Category 1 consistent with RG 1.97. However, since Fort St. Vrain has one additional barrier to fission product release, namely confinement or reactor building, this has also been included. Since this additional group of variables for Fort St. Vrain represents additional margin over these LWR variables, it is considered that upgrade of these three variables (C20, C21 and C22) to Category 2, in addition to the variables for fuel particle coating integrity, liner and primary closure integrity, and PCRV concrete and secondary closure integrity meets or exceeds the intent of RG 1.97.

Attachment 1 to P-86460

2. Exception:

Radwaste system - the licensee should verify that all their radwaste systems have appropriate instrumentation (Section 3.3.3)

Response

As stated in Section IV 'of the original submittal, the parameters selected for Fort St. Vrain were based upon a

, detailed analysis of the effects and conditions of the accidents delineated in DBA-1 (Permanent Loss of Forced Circulation), DBA-2 (Rapid Depressurization/ Blowdown), the Max 1aum Credible Accident, or the Loss of Normal Shutdown Cooling as defined in the FSAR. Since none of these accidents involve the radioactive liquid waste system or the radioactive gas waste system, parameters associated with these systems are not required for post accident monitoring and therefore they have not been and need not be included in PAM instrumentation.

3. Exception:

i Ventilation system - the licensee should provide Category 2 instrumentation for this variable (Section 3.3.3).

Response

PSC concurs with this recommendation and -will upgrade Variables D-31 (Damper Position for Control Room Emer Air Flow) and D-32 (Reactor Building Vent Exhaust Flow)gency from Category 3 to Category 2.

4. Exception:

Power supplies - the licensee should provide Category 2 instrumentation for this variable (Section 3.3.3).

Response

PSC concurs with this recommendation and -will upgrade Variables D-33 (Essential 480V Bus Voltage) D-34 (Essential 480V Bus Current) and D-35 (Essential 125V Bus Voltage) from 4

Category 3 to Category 2.

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Attachment 1 to P-86460

5. Exception:

Reserve shutdown system - the licensee should identify the key variable for this instrumentation group and upgrade the instrumentation for this variable to Category 2 (Section 3.3.3).

Response

The key variable for monitoring the proper performance of the Reserve Shutdown System is Bottle Pressure (Variable D-18). Per the recomendation, PSC will upgrade this variable from Category 3 to Category 2.

6. Exception:

Reactor plant cooling system - the licensee should identify the key variable for this instrumentation group and upgrade the instrumentation for this variable to Category 2 (Section 3.3.3).

Response

The key variables for monitoring the proper performance of the Reactor Plant Cooling System are PCRV Subheader Flows (D-19) and PCRV Bottom Penetrations, Bottom Head, Barrel and Top Head, Circuit Inlet Header Temperature (D-21). Per the recommendation, these components will be upgraded from Category 3 to Category 2.

7. Exception:

Purification cooling water system - the licensee should identify the key variable for this instrumentation group and upgrade the instrumentation for this variable to Category 2 (Section 3.3.3)

Response

The key variable for monitoring the proper performance of Purification Cooling Water System is Purification Coolin Water Heat Exchanger Outlet Temperature (Variable D-23)g .

Per the recommendation, PSC will upgrade this variable from Category 3 to Category 2.

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to P-86460

8. Exception:

Helium purification system - the licensee should identify the key variable for this instrumentation group and upgrade the instrumentation for this variable to Category 2 (Section 3.3.3).

Response

The key variables for monitoring the proper performance of the Helium Purification System are Helium Purification Dryer Outlet Temperature (D-26) and Helium Purification Low Temperature Adsorber Outlet Temperature (D-27). Per the recommendation, PSC will upgrade this variable from Category 3 to Category 2.

9. Exception:

Nitrogen system - the licensee should identify the key variable for this instrumentation group and upgrade the instrumentation for this variable to Category 2 (Section 3.3.3).

Response

The key variable for monitoring the proper performance of the Nitrogen System is Storage Tank Level (Variable D-30).

Per the recommendation, PSC will upgrade this variable from Category 3 to Category 2.

10. Exception:

Steam generator pressure -

the licensee should provide Categ ry 2 instrumentation for this variable (Section 3.3.3 .

Response

PSC concurs with this recommendation and will upgrade Variables D-15 (Steam Generator EES Outlet Pressure) and D-16 (Steam Generator HRH Outlet Pressure) from Category 3 to Category 2.

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Attachm:nt 1 to P-86460

11. Exception:

Area radiation - the licensee should. provide the recommended instrumentation for the reactor building (Section 3.3.4).

Response

The attached Enclosure A contains the listing of Area Radiatian Monitors that PSC recommends be added to the PAMI listing to resolve this exception. Enclosure A lists the design information for each of the components added via this Variable E.4a. The range of the refueling floor high range area monitor (RT-93250-14) envelopes the maximum expected radiation level in the area as a result of DBA-2. All other area monitors would be used to help evaluate personnel entry following any accident into areas containing safe shutdown equipment.

12. Exception:

Environs radiation and radioactivity - the licensee should provide additional information on the instrumentation supplied for these variables (Section 3.3.4).

Response

Enclosure B contains a list of the various portable radiation monitors that PSC will utilize following the Design Basis Accidents. Note that this instrumentation is designated as Category 3.

13. Exception:

Estimation of atmospheric stability - the licensee should install instrumentation with the recommended ran or justify the use of the existing instrumentation (ge Section 3.3.4)

Attachment 1 to P-86460

Response

PSC has previously installed atmospheric stability instrumentation to comply wit.h RG 1.23. The existing temperature differential instrumentation measures the temperature between 10m and 58m with a range of -5 degrees F to +5 degrees F.

RG 1.23 requires that differential temperature instrumentation is capable of adequately measuring temperature changes with height to determine the atmospheric stability per table 1 of RG 1.23. The bounding parameters are listed below.

Stability Pasquill Temperature Change Classification Categories with Height Extremely Unstable A <-1.9 degrees C/100m =

-3.42 degrees F/100m Extremely Stable G > 4.0 degrees C/100m =

7.2 degrees F/100m Considering that the temperature differential measurement is taking place over a vertical tower length of 48m (meters),

this translates into a maximum span of -1.64 degrees F to

+3.46 degrees F. With the appropriate accuracy of +.9 degrees F, the range of -5 degrees F to +5 degrees F is considered adequate.

! ENCLOSURE A AREA RADIATION MONITORS -

FOR POST ACCIDENT MONITORING (VARIABLE E-4a) .

INSTRUMENT CTL ROOM CAT NO RANGE DISPLAY EOF /TSC VARIABLE (NOTE 2) (NOTE 3) (NOTE 4) .(NOTE 5) (NOTE 6) PURPOSE COMMENTS E.4a.1 Rx Plant Exhaust 3 RT-93251-1 .1R to 1E+4R RIS-93251-1 No Verify significant High Range Monitor Filter Rm - Tb releases and local Turbine Building magnitudes E.4a.2 South Stairwell-Rx 3 RT-93252-2 .1 mR to IE+4mR RIS-93252-2 Reactor Building E.4a.3 Mn Ctl Rm-Tb 3 RT-93250-5 .1 mR to 1E+4mR RIS-93250-5 Turbine Building E.4a.4 Gas Waste Filters 3 RT-93251-5 .1 mR to 1E+4mR RIS-93251-5 Reactor Building E.4a.5 South Stairwell-Rx 3 RT-93252-6 .1 mR to IE+4mR RIS-93252-6 Reactor Building E.4a.6 Valve Oper Stat - 3 RT-93251-7 .1 mR to IE+4mR RIS-93251-7 Reactor Building West - Rx E.4a.7 Valve Oper Stat - 3 RT-93252-7 .1 mR to 1E+4mR RIS-93252-7 Reactor Building East - Rx E.4a.8 NE Walkway - Rx 3 RT-93250-8 .1 mR to 1E+4mR RIS-93250-8 Reactor Building E.4a.9 Buffer Hel Dry 3 RT-93251-9 .1 mR to 1E+4mR RIS-93251-9 Reactor Building Stairwell Loop 1 -

Rx E.4a.10 Condensate Demin. - 3 RT-93250-13 .1 mR to IE+4mR RIS-93250-13 Turbine Building Tb-E.4a.11 E. Wall Refueling 2 RT-93250-14 .1 mR to 1E+4R RIS-93250-14 High Range Monitor j Floor - Rx Reactor Building

• Notes apply to original PAM submittal, Reference 1. r3

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ENCLOSURE B-PAMI PORTABLE RADIATION MONITORS INSTRUMENT CTL ROOM CAT NO RANGE DISPLAY EOF /TSC VARIABLE (NOTE 2) (NOTE 3) (NOTE 4) (NOTE 5) (NOTE 6) PURPOSE E5 Portable Radiation 3 R0-5 ImR-200R No No Verify significant Instrumentation / R0-7 200R-20,000R No No releases and local Sensors SAM-II 1E-10 to No No magnitudes SE-5 micro Ci/cc Iodine i

i o Notes' apply to original PAM submittal, Reference 1.

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Attachment 2 to P-86460 ATTACHMENT 2 PAMI CATEGORY 2 UPGRADE MATRIX DEFINITION OF FIELDS ITEM N0.: This field lists the variable number for the PAMI parameter as it appears on FSV RG 1.97 PAMI Table.

INSTRUMENT NO.: Self explanatory.

VARIABLE: This field provides the description of the PAMI variable listed.

REQUIRED TO This Field notes ("X") which of the following MONITOR accident (s) that the PAMI variable is required FOLLOWING to monitor:

ACCIDENT (S):

- DBA Design Basis Accident 1

- DBA Design Basis Accident 2

- LNSC - Loss of Normal Shutdown Cooling

- MCA - Maximum Credible Accident

- HELB - High Energy Line Break PLANT This field defines the physical location in the plant in which the SENSOR and CABLE are located:

RB - Reactor Building TB - Turbine Building OS - Outside the RB or TB SWR - Switchgear Room AX - Aux. Electric Room EQ REQUIRED This field denotes the Environmental Qualification FOR MONITORING (EQ) level required (HARSH / MILD) to ensure the ACCIDENT (S): (HARSH / MILD) to ensure the operability of the variable sensor and cable during the accident it is required to monitor. An 'X' in the HARSH column denotes that both the sensor and cable require EQ qualification per 10 CFR 50.49. The word CABLE in the HARSH column denotes mild EQ of the sensor but harsh EQ of the cable.

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Attachment 2 to P-86460 1.97 CATEGORIES: This field notes the requirement to upgrade each Category 3 variable listed to Category 2 per the guidelines contained in Reg. Guide 1.97.

UPGRADE BASIS: This field denotes the basis for the upgrade from Category 3 to Category 2. An X in the KEY VARIABLE column identifies the upgrade resulting from the response to Reference 2. An X in the HARSH ENVIRONMENT column identifies the upgrade based on the need for equipment operability in a harsh environment (for HELB or DBA 2 accidents). In some cases, both columns have an X. ,

NOTE: Variable D37 has been revised from the original PAM

< submittal per Reference 1 as follows:

Control Room Instrument No. Range Display EOF /TSC PT-91141 2000-3500 PSIG PI-91141 NO PT-91142 2000-3500 PSIG PI-91142 N0 I

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PAMI ChTEGORY 2 VARIABM UPGRADES EQ RIQUIRED REQUIRED TO MOKITOR PIJuff FOR MONITORING 1.97 FOLIntrING ACCIDElft(S) IDCATION M MHr(S) CATEGORY UPGIRADE IIASIS ITEM KEY BARSH NO. IIIS11ttBEDrr MO. VARIABLE DBA1 DBA2 IMIC BECA BELB SENSOR ChBIE EARSE MIID WIGIIIAL UPGRADE VARIABIJE EBR4N E3 PT-2409 Reserve Shutdown X RB RB X 3 2 X System Bottle (For D18)

Pressure B4 TE-11101-1,2,3,4 Core Outlet X X X X RB RB X 3 2 X thru Temperature TE-11137-1,2,3,4 M TE-1171 He Circulator X X X X RB RB X 3 2 X thru Inlet Temperature TE-1378 E26 TE-11101-1,2,3,4 Core Outlet X X X X RB RB X 3 2 X thru Temperature TE-11137-1,2,3,4 C2 RT-9301 Reactor Coolant X X X X X RB RB X 3 2 X System Activity C4 TE-11101-1,2,3,4 Core Outlet X X X X RB RB X 3 2 X thru Temperature TE-11137-1,2,3,4 C5 TE-1171 Helium Circulator X X X X RB RB X 3 2 X thru Inlet Temperature TE-1178 N

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i PANI CATEGORY 2 VARIABIR UPGRADES NQ REQUIRED REQUIRED TO NDNITOR PLANT POR NOMITEEtING 1.97 FOLIDWING ACCIDENT (S) IaCATION ACCIDENT (S) CATEGORY UPGRADE BASIS ITEBt REY EARSH NO. INSTRIBEENT NO. VARIABI2 DBA1 DBA2 IMIC BACA HEIA SENSOR CABIA MARSH MIIa ORIGINAL UPGRADE VARIABIE ENVIFM C30 PS-7377-1 thru -20 Louver Position X X RB RB X 3 2 X PS-7382-1 thru -20 via Pressure Indication C21 PT-73335 Reactor Building X X RB RB X 3 2 X PT-73440 Pressure thru PT-73452 C32 PDT-7319-1 Refueling Floor to X X RB RB X 3 2 X thru Ambient Differen-PDT-7319-4 tial Pressure D4 PDT-2147 Bearing Water Surge X X X X RB RB X 3 2 X PDT-2148 Tank to PCRV Differ-ential Pressure D3 LT-21135 Bearing Water Surge X X X X RB RB X 3 2 X LT-21136 Tank Level D6 FT-21833 FT-2184 Bearing Water Flow X X X X RB RB X 3 2 X FT-21853 FT-2186 D8 LT- 4102-1,2 Storage Basin Level X X OS TB Cable X 3 2 X D12 TE-22121 Steam Generator EES X X X X RB RB X 3 2 X TE-22122 Outlet Temperature N

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b PANI CATurzwY 2 VARIAn;2 UFCRADES EQ W RED REQUIRED TO SONITOR PLAarr Pm NOIEITGtING 1.97 POLIEBfING ACCIDBart(S) IDCATION ACCIDIDft(S) CATEGORY UP(HADE BASIS 3T33: KEY HARSS NO. INSTRIBIEIrr MD. VARIABI2 DBA1 DBA2 IMIC IOCR EERIA muuasnR CABIE HARSH MIID MIGIIIAL UFCRADE VARIABIJ: EBfVI N D15 PT-22129-1 Steam Generator EES X X X X RB RB X 3 2 X X PT-22130-1 Outlet Pressure D16 PT-2267 Steam Generator HRH X X X PT-2268 Outlet Pressure D17 LT-4102-1,2 Storage Basin Ievel X X OS TB Cable X 3 2 X D18 PT-2409 Reserve Shutdown X RB RB X 3 2 X System Bottle Pressure D19 36 FTs PCRV Subheader X RB RB X 3 2 X Flows D31 TE-4637-1 PCRV Bottom X RB RB X 3 2 X TE-4638-1 Penetrations Bottom Head, Barrel & Top Head, Circuit Inlet Header Temperature D33 TE-2321-1 Purification X RB RB X 3 2 X TE-2321-2 Cooling Water Heat Exchanger Outlet Temperature N

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2 PANI CATEGORY 2 VARIABIR UPGRADES BQ REQUIRED REQUIRED TO MONITOR FIANT FOR MONITORING 1.97 FOLIONING ACCIDENT (S) IOCATION ACCIDENT (S) CATBGuaY UPGRADE BASIS ITFE KEY BAkSH NO. IMB11t0NENT NO. VARTAP.IR D8A1 DBA2 Ymmr* MCA BEIR SM CABIR MARSE MIID ORIGIMAL UPGItADE VARIABIE ENWIR(MEBPF D36 TE-23105 Helium Purifica- X RB RB X 3 2 X TE-23106 tion Dryer Outlet Temperature D37 TE-2322-3 Helium X RB RB X 3 2 X TE-2322-4 Purification Low Temperature Adsorber Outlet Temperature D29 PT-4229 Service Water Pump X X X X X TB TB X 3 2 X Header Discharge Pressure D30 LT-2519-1 Nitrogen Storage X RB RB X 3 2 X Tank Iavel D31 See Note 9 Damper Position X X X X TB TB X 3 2 X of PAMI for Control Room Submittal Emergency Air Flow D33 FT-7320 Reactor Building X X TB TB X 3 2 X Ventilation Exhaust Flow r+

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4 PANI CATMQ(EtY 2 VARIABIR UPGRADES no RaQUIRED REQUIRED TO BEMiI10R PIJurr FOR N0EITORING 1.97 FOLIDf1NG JWXIIDigrt(S) IDCATION ACCIDEBrt(S) CATEGORY UPGBADE HASIS ITEst REY HARSH NO. IMSTRIBEIBrr 30. VARIABIE DBA1 DBA2 IMIC IER REIA famMM CARIA BARSH MIID MIGIHAL UPGRADE VARIARIA DVIROmegrF D33 PT For Essential 480V Bus X X X X X SWR TB Cable X 3 2 X X EI-9273A Voltage EI-9274 EI-9275A D34 CT For Essential 480V Bus X X X X X TB TB Cable X 3 2 X X II-9244 Current 11-9248 D35 ET-92220 Essential 125V Bus X X X X X SWR AX X 3 2 X ET-92221 Voltage (DC)

D36 PT-8212 Instrument Air X X X X X TB TB X 3 2 X PT-8254 Receiver Pressure D37 PT-91141 Hydraulic Icop X X X X RB RB X 3 2 X PT-91142 Pressure

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