ML20127K094

Responds to Generic Ltr 83-28.Forwards Table Demonstrating post-trip Review Capabilities Based on Evaluation of Digital & Analog Parameters Telemetered Into Plant Computer Re Table 1.3 of Draft Technical Evaluation Rept (G-85189)

ML20127K094
Person / Time
Site:	Fort Saint Vrain
Issue date:	06/12/1985
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:	Johnson E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
GL-83-28, P-85204, TAC-52840, TAC-53591, NUDOCS 8506270256
Download: ML20127K094 (8)

Text

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Company of Colorado 16805 WCR 19 1/2, Platteville, Colorado 80651 June 12, 1985 Fort St. Vrain

]ggQQ Unit No. 1 P-85204 Regional Administrator Region IV Jgg 18 EE5 Nuclear Regulatory Commission y 611 Ryan Plaza Drive, Suite 1000 . -

Arlington, Texas 76001 ATTN: Mr. E. H. Johnson Docket No. 50-267

SUBJECT:

Response To Generic Letter 83-28

REFERENCES:

1) G-85180, Johnson to Lee, Dated May 9, 1985.

2) P-83359, Lee to Eisenhut, Dated November 4, 1983.

3) G-85189, Johnson to Lee, Dated May 17, 1985.

Dear Mr. Johnson:

We have reviewed your " Request for Information" (G-85180, Ref. 1) relative to Generic Letter responses transmitted to the Nuclear Regulatory Commission on November 4, 1983 (P-83359, Ref. 2) .

Additionally, we have reviewed the Draft Technical Evaluation Report (TER) for Salem'ATWS Item 1.2 (G-85189, Ref. 3) . We have evaluated our digital and analog parameters telemetered into the plant computer relative to Table 1.3 of the TER, and have prepared a detailed table demonstrating our post-trip review capabilities. Our responses to these items or inquiries are addressed in the attachment to this letter.

If you have any questions, please contact Mr. Frank Novachek at (303) 785-2223, Ext. 201.

Sincerely, EU aknkg J. W. Gahm ,

Manager, Nuclear Production

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. P-85204 Attachment Page 1 of 7 PUBLIC SERVICE COMPANY OF COLORADO RESPONSE TO REQUEST FOR INFORMATION FORT ST. VRAIN RESPONSE TO GENERIC LETTER 83-28 l

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- P-85204 Attachment Page 2 of 7 Item 1.2 POST TRIP REVIEW PARAMETER LIST-PLANT COMPUTER Time Sequence of History Events Recorder Recorder Parameter / Signal ,

Instrument X Manual Scram HS-9330 X Reactor Trip-Scram Contacts K-52 and K-53 X Turbine Trip XRA-92122 X Control Rod Position ZT-1233-1 to (Analog Signals) ZT-1233-37 X (*) Neutron Flux, Power NIM-1133-3 (Analog Signals) NIM-1134-3 NIM-1135-3 NIM-1136 to NIM-1138 X Neutron Flux, Power NSH-1133-6 (Scram, Reactor Power High) NSH-1136-4 X Reactor Building Temperature TSH-93472 (Scram)

X (*) Reactor Building Radiation RIS-93250-10 (Analog Signals) RIS-93250-11 RIS-93252-12 X Reactor Pressure High PSH-1108-1 (Scram)

X Reactor Pressure Low PSL-1108-1 (Scram)

X (*) Reactor Pressure PT-1110 l

(Analog Signal)

X Core Region Outlet TE-11101-2 Temperature (Analog Signal) to TE-11137-2 X Circulator Inlet Temperature TE-1171 to (Analog Signal) TE-ll78 X Circulator Speed - Trips:

A Circulator Speed Fixed High SAH 9381

. A Circulator Speed Programmed Low SAL-9383 B Circulator Speed Fixed High SAH-9397 B Circulator Speed Programmed Low SAL-9399 i C Circulator Speed Fixed High SAH-9382 C Circulator Speed Programmed Low SAL-9384 D Circulator Speed Fixed High SAH-9398 D Circulator Speed Programmed Low SAH-93100

• P-85204 Attachment Page 3 of 7 Time Sequence of History Events Recorder Recorder Parameter / Signal Instrument X- (*) Circulator Speed ST-2105 (Analog Signal) ST-2111 ST-2106 ST-2112 X (*) Circulator Seal Malfunction FAL-93107 (Buffer /Mid-Buffer Trip) FAL-93109 FAL-93108 FAL-93110 X Circulator Bearing Water Malfunction FAL-93103 (Low Bearing Water Flow Trip) FAL-93105 FAL-93104 FAL-93106 X (*) Circulator Bearing Water Flow FM-2183 (Analog Signal) FM-2185 FM-2184

'FM-2186 X Circulator Drain Malfunction PDAL-93269 (Circulator Trip) PDAL-93271 PDAL-93270 PDAL-93278 X Circulator Penetration Overpressure PAH-93325 (Circulator Trip) PAH-93327 PAH-93326 PAH-93328 X (*) Primary System Flow PDM-1157-2 (Analog Signal) PDM-1157-1 PDM-1159-2 PDM-1159-1 i

PDM-1158-2 i

PDM-1158-1 PDM-1160-2 PDM-1160-1 l

X Primary System Moisture MI-9306 l MI-9307 X Loop Shutdown Moisture High MAH-9369 MAH-9370 X Reheat Steam Isolation Valve ZI-2253-1 Position .ZI-2254-1 X Main Steam Stop Check Valve ZI-2223-1 Position ZI-2224-1 l

X Main Steam Pressure (Scram) PAL-9338 X (*) Main Steam Pressure PT-22129 (Analog Signal) PT-22130 i

.- P-85204 Attachment Page 4 of 7 Time Sequence of History Events Recorder Recorder Parameter / Signal Instrument X Main Steam Temperature TAL-9378 (Loop Shutdown) TAL-9374 X (*) Main Steam Temperature TM-2225-6 (Analog Signal) TM-2226-6 X Hot Reheat Steam Pressure (Scram) PAL-9339 X Hot Reheat Steam Pressure PT-2267 (Analog Signal) PT-2268 X Hot Reheat Steam Temperature (Scram) TAH-9333 X (*) Hot Reheat Steam Temperature TM-2256-7 (Analog Signal)

X Hot Reheat Steam Activity RAH-9371 (Loop Shutdown) RAH-9372 X (*) Hot Reheat Steam Activity RIS-93250-10 (Analog Signal) RIS-93250-ll Steam Generator Level Not ApplicabL X Steam Generator Penetration PAH-93365 Overpressure (Loop Shutdown) PAH-93366 X Feedwater Flow FAL-93355 FAL-93357 (Circulator Trip)

FAL-93356 FAL-93358 X (*) Feedwater Flow FM-2205-6 (Analog Signal) FM-2206-6 X Steam Flow - Loop Feedwater Flow FM-2205-6 (Analog Signal) FM-2206-6 X Emergency Feedwater Flow FM-2297 X Emergency Feedwater Valve Position ZI-2203-1 ZI-2204-1 i X AC and DC System Status:

AC System 230 KV OCBS - North Bus OCB-5300

[ South Bus OCB-5301

! RAT OCB-5305 Lookout-RAT OCB-5306 Lookout OCB-5307 Smokey Hill OCB-5309 Smokey Hill-Pawnee OCB-5310 Pawnee OCB-5311 i PRPA OCB-5313 Weld OCB-5315 PRPA OCB-5317 4

I c

P-85204 Attachment ,

Page 5 of 7 Time Sequence of History Events Recorder Recorder Parameter / Signal Instrument 4160 Volt-4KV Bus 1A Feed HS-9203 4KV Bus IB Feed HS-9207 4KV Bus 1C Feed HS-9205 Load Center Aux Transformer 480 Volt AC Load Center 125 Volt DC Bus Voltage Instrument Bus Voltage 4KV Tie Bus 2 to Bus 1 HS-9209 4KV Tie Bus 2 to Bus 3 HS-9211 4KV Feed to 480 V Tran 1 HS-9213 4KV Feed to 480 V Tran 2 HS-9214 4KV Feed to 480 V Tran 3 HS-9215 4KV Feed to 480 V Tran 4 HS-9216 4KV Feed to 480 V Tran 5 HS-9217 4KV Feed to 480 V Tran 6 HS-9218 4KV Feed to 480 V Tran 7 HS-9219 Turbine Building HVAC Tran 8 152-TR8 Reactor Building HVAC Tran 9 152-TR9 4KV Tie HVAC to 152-1 152-RAT 4KV Tie HVAC to ACM Bus 152-1 4KV ACM to 480 V ACM 152-ACM 480 V Main Feed Bus 1 HS-9221 480 V Main Feed Bus 2 HS-9223 480-V Main Feed Bus 3 HS-9225 480 V Main Feed Bus 4 HS-9227 480 V Main Feed Bus 5 HS-9229 480 V Main Feed Bus 6 HS-9231 480 V Main Feed Bus 7 HS-9233 480 V Tie Bus 1 to Bus 2 HS-9235 480 V Tie Bus 3 to Bus 2 HS-9237 480 V Tie Bus 4 to Bus 5 HS-9239 480 V Bus 1 to A Instr N-9236 480 V Bus 2 to B Instr N-9236S X Diesel Generator Status:

A Standby Generator Run HS-9244 B Standby Generator Run HS-9248 Standby Generator Overvoltage CR-9207 CR-9208 PCRV Relief Valve Isolation Valve Locked Open Position

(*) Indicates a parameter which is also recorded on a chart recorder.

• P-85204 Attachment Page 6 of 7 Item 2.1 (First Part)

Public Service Company of Colorado (PSC) is currently involved in a program to completely rewrite the plant's maintenance procedures and will identify all RTS components as safety related in these revised procedures. These procedure revisions are expected to be completed by January 3, 1986.

Item 2.1 (Second Part)

Public Service Company of Colorado will continue to seek assistance and Equipment Technical Information (ETI) from other safety-related equipment vendors when our evaluation of an equipment or ETI problem concludes that such direct interaction is necessary, or would be beneficial. These situations and those of a lesser nature will, of course, be reported by means of NPRDS and/or the SEE-IN program.

Public Service Company of' Colorado will ensure that the information gained from the vendor interface program is incorporated into the operation, maintenance, and test procedures in the following manner:

A. All vendor information will be routed to single responsible organization.

B. All vendor information will be logged as it is recieved.

C. All vendor information will be reviewed by the plant engineering group for applicability to procedures, and will be submitted to the Operating Information' Assessment Group (OIAG) for action.

D. Procedures will be updated as appropriate.

J E. Results and recommendations of vendor information review will be documented and tracked via OIAG files and the Production Commitment Log.

Item 2.2.2 The Vendor Equipment Technical Information Program (VETIP) as defined in the March 1984 NUTAC document is considered a valid response to Section 2.2.2 of the Nuclear Regulatory Commission Generic Letter 83-28. Public Service Company of Colorado has implemented a majority of the program as described therein. Unincorporated portions of that program are described in the response to Item 2.1 (Second Part) above, and are in the process of implementation. Accordingly, it is requested that the Nuclear Regulatory Commission reanalyze and reconsider their request for additional information.

-1 e 1 P-85204 Attachment Page 7 of 7 Item 3.1.3 No post maintenance testing requirements for RTS components have been I found in the Technical Specifications that degrade, rather than I enhance, safety.

Item 3.2.3 No post maintenance testing requirements for non-RTS safety related components have been found in the Technical Specifications that degrade, rather than enhance, safety.

Item 4.5.3 Existing intervals for the on-line functional testing required by the Technical Specifications were reviewed by Public Service Company of Colorado. A Technical Specification change to Limiting Condition for Operation 4.4.1 (Plant Protective System) and its asscoiated surveillance requirements (SR 5. 4.1) are currently being reviewed by the Plant Operations Review Committee (PORC). This Technical Specification change is expected to be approved by the PORC and the Nuclear Facility Safety Committee (NFSC) by June 30, 1985. As part of the development process for these proposed changes to the Technical Specifications, on-line functional testing intervals were reviewed based on past experience. Possible changes to the testing intervals in certain cases where available test data may support such changes has been discussed at length with Nuclear Regulatory Commission staff. The Nuclear Regulatory Commission staff has informed Public Service Company of Colorado that no such changes would be acceptable at this time.