ML20214H650

Discusses Status of Augmented Sys Review & Test Program (Asrtp) Program.Asrtp Insp Items Processed Into Plant Performance & Mgt Improvement Program for Validation, Approval,Implementation & Closure

ML20214H650
Person / Time
Site:	Rancho Seco
Issue date:	05/15/1987
From:	Andognini G SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Partlow J Office of Nuclear Reactor Regulation
References
GCA-87-046, GCA-87-46, NUDOCS 8705270450
Download: ML20214H650 (9)

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SACRAMENTO MUNICIPAL UTILITY DISTRICT O P. O. Box 15830, Sacramento CA 95852-183'),(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CAUFORNIA h04Y 151987 GCA 87-046 James Partlow, Director Division of Reactor Inspection and Safeguards Office of Nuclear Reactor Regulation Washington, DC 20555 Docket 50-312 Rancho Seco Nuclear Generating Station Unit #1 AUGMENTED SYSTEMS REVIEW & TEST PROGRAM (ASRTP) INSPECTION

Dear Mr. Partlow:

The District is committed to the safe and reliable operation of Rancho Seco.

This commitment demands a careful self-examination following the recent ASRTP Inspection, looking beyond the specific Inspection findings to identify broader implications and, as necessary, programmatic improvements.

The District is pursuing the implications of the ASRTP Inspection. All ASRTP Inspection items have been processed into the Plant Performance and Management Improvement Program (PP&MIP) for validation, approval, implementation, and closure. All ASRTP Inspection items will be addressed in accordance with the existing PP&MIP mechanism which is the District's basis to delineate a phased approach to performance improvement and restart of Rancho Seco. The District will provide a detailed response to the ASRTP Inspection Report 50-312/86-41 in a complete, formal reply prior to the scheduled followup inspection visit.

The District recognizes the importance of establishing the specific listing of items the District will complete prior to restart. Revision 0 of the Restart Scope List was transmitted for J. B. Martin, RV Administrator, on April 17, 1987. This submittal provides a basis for discussion and concurrence by NRC staff on the District's plant for restart of the unit. ASRTP Inspection items will be integrated into the Restart Scope List.

As committed to Joe Callan, NRC ASRTP Inspection Team Leader, this letter forwards the attached summary of ASRTP Inspection items for which the District plans to provide a resolution prior to restart.

The District would like to express its appreciation for your Inspection efforts. The review was thorough, the findings relevant, and the interaction constructive. More particularly, the inspection has been a helpful course check on the District's road to restarting Rancho Seco. It has helped the 8705270450 870515 t PDR ADOCK 05000312 G PDR 2 fp

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RANCHO SECO NUCLEAR GENERATING STATION fJ 14440 Twin Cities Road, Herald, CA 95638-9799;(209) 333-2935

~ James Partlow -2_: 404Y 151987 GCA 87-046 Nuclear,0rganization maintain its focus on quality implementation and attention to_datail. The District realizes that quality of operational performance is absolutely essential for public trust and confidence, and that credibility rests on promises kept.

Sincerely,_

$. df.a:4I Carl And nini l

Chief Executive Officer, Nuclear-Attachment ec: J. Callan, NRC, Bethesda A. D'Angelo, NRC, Rancho Seco J. Dyer, NRC, Bethesda G. Kalman, NRC, Bethesda (2)

J. B. Martin, NRC, Walnut Creek T. O. Martin, NRC, Bethesda

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ASRTP Inspection Response Items Committed for Resolution Prior to Restart ASRTP'IR; Item f

_ . Associated QTS #

^(ASRTP Report Reference). Summary Item Description .(QCI-12 Priority)

' Item 86-41-01 Resolve P-318 motor overspeed concerns 26.1069-f(Section'3.1.1(1)) (AFW SSR Problem #61). (1)

Item 86-41-01 Perform appropriate testing to 26.0608 (Section 3.1~.1(2)) evaluate need for procedura1' caution (1) against quick restarting of AFWPT (AFW SSR Problem #31).

Item 86-41-02 Install flow limiting verturis to

• 26.0957 (Section 3.1.1(3)) prevent excessive AFW flow to'OTSGs (1)

(AFW SSR: Problem #54, ECN f R-1672A).

Item 86-41-03. Modify AFW Full Flow Test Line to

• 26.0120 (Section 3.1.1(4)) provide _for accurate surveillance (1)-

testing (AFW SSR Problem 3, ECN #

R-1188).

Item 86-41-04 Evaluate AFW Pump Runout effects due 15.0282 (Section'3.1.1(5))- 12/26/85 event-(AFW SSR Problem #43). - (1)-

-Item 86-41-04 Evaluate the effects of cumulative 26.1064 (Section 3.1.1(5)) AFW Pump runout (AFW SSR Problem #56). (2R)

Item 86-41-04 Evaluate the potential for AFW Pump 26.1081

-(Section 3.1.1(5)) runout following installation of EFIC (2R) and flow limiting venturis (AFW SSR Problen #66).

Item 86-41-05 __

Verify accuracy of AFW Pump Per- 26.1084 (Section 3.1.1(6)) formance Calculation Z-FWS-M2081 (1)-

(AFW SSR Problem f55).

Item 86-41-06 Assure adequate overpressure pro- 26.1087 (Section 3.1.2(1)) tection for main and startup feed- (2R) water control valve actuators.

Item 86-41-06 Document seismic qualification of 26.1088 (Section 3.1.2(2))- safety related valves in backup air (1) supplies for EFIC modifications.

~ Item 86-41-06 Replace excess flow check valves in 26.1089 (Section 3.1.2(3a&b))- backup air supplies. (1)

• Committed to in 2/12/87 ASRTP Inspection Exit Interview

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ASRTP Inspection Response-Items Committed for Resolution Prior to Restart ASRTP-IR' Item # Associated QTS f (ASRTP Report Reference) Summary Item Description (OCI-12 Priority)

_ Item 86-41-06 . Establish operating procedures to moni- 26.1090 (Section 3.1.2(3c)) tor backup bottle pressure and initiate (2R) appropriate actions if leakage is indi-cated.

Item 86-41-06 Establish periodic test procedures to _26.1091 (Section 3.1.2(3d)) functionally verify the bottle backup (2R).

air systems.

- Item 86-41-06 Resolve concerns that pressure' control 26.1092 (Section 3.1.2(4))- valves'for EFIC backup air system may (2R) not be appropriate design application.

Item 86-41-06 Verify accuracy of fabrication drawings '

26.1093 (Section 3.1.2(5)) for EFIC backup air supplies. (1)

Item 86-41-07 Resolve FWS SSR Problem #6 relating to 20.0043

. (Section 3.1.3) faulty MFF Lovejoy Control Response (2R)

- (Implement ECN #R-0717).

Item 86-41-07 Resolve FWS SSR Problem #12 relating to 20.0188 (Section 3.l.3) MFW control valve positioning during (2R) transients.

Item 86-41-07 Resolve FWS SSR Problem #18 relating to 22.0330 (Section 3.1.3) Casualty Procedure C.26 enhancements. (2R)

Item 86-41-07 Resolve FWS SSR Problem #19 relating to 22.0453 (Section 3.1.3) Casualty Procedure C.10 enhancements. (2R)

" Item 86-41-07 Resolve FWS SSR Problem #22 updating 22.0688 (Section 3.1.3) P&ID M-580, Sheet 1. (2R)

Item 86-41-07 Resolve FWS SSR Problem f45 relating to 26.0518 (Section 3.1.3) MFP governor response (Implement ECN (2R)

R-0717).

Item 86-41-08 Docunent environmental qualification of 26.1086 (Section 3.1.4(1)) excess flow check valves installed in- (1)

EFIC sensing lines.

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• Committed to in 2/12/87 ASRTP Inspection Exit Interview 3

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ASRTP: Inspection Response j-0 Items Committed'for Resolution' Prior to Restart (Y

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fASRIP IR Item #L .

. Associated-QTS #

(ASRTP Report Reference) Summary Item Description (QCI-12 Priority)

Item 86-41-09 . Revise and resubmit EFIC. Safety Analys'is 25.1061 (Section 3.1.4(2)) to more clearly reflect EFIC sensing (1)

,g , line design.

f" (Item.86-41-09.. Document evaluation of acceptability 26.1085 (Section 3.1.4(2)) of operational procedures and training (2R)

-for response to EFIC sensing line failures.

Item 86-41-10 Incorporate appropriate-provisions to 26.1098 (Section 3.1.4(3)) - fully test the EFIC maintenance bypass. (1) feature.

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Item 86-41-11' ft Resolve 125 VDC System SSR Problem #8

• 26.0218 (Section.3.1.5(1))~' relating to Procedure A.61 enhancements. (2R)

Item 86-41 Resolve:125 VDC System SSR Problem #9

• 26.0219 (Section 3.1.5(2)) . relatin8 to maintaining battery room (2R)

'b . temperatures within design temperature limits.

i Item 86-41-11 ' Resolve.125 VDC System SSR Problem #20

• 26.0987 (Section 3.1.5(3)) relating to refurbishment of six AB (2R) j< battery chargers.

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N Item 86-41-11 .

Resolve 125 VDC System SSR Problem #22

• 26.0989 h ' relating to open NCRs on deformed (Section 3.1.5(4)) (2R) battery terminal posts.

ii[ Item 86-41-12 .

Resolve 120 VAC System SSR Problem #7 .

• 26.0353

'(Section 3.1.6(1))' updating the IEB 79-27 study to include (1) all changes to the 120 VAC vital buses, i ,

. Implement the recommendations of the IEB

! . ,;, z. , 79-27 study.

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"i -Item 86-41-12 Address 120 VAC System SSR Problem #2

• 22.0384 (Section 3.1.6(1)) ,

relating to CR annunciation of feeder (3R) s ,'

breaker trips. An overview study will be done to provide a resolution of identified concerns.

1 0 ' Committed to in 2/12/87 ASRTP Inspection Exit Interview

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'ASRTP Inspection Response -

Items Committed for Resolution Prior to Restart ASRTP-IR Item =f ' Associated QTS #

~(ASRTP Report Reference) Summary Item Description (QCI-12 Priority)

. Item 86-41-12 -

Resolve 120 VAC System SSR Problem #5

• 26.0266

-(Section 3.1.6(1)) relating to casualty procedures for (2R) loss of 120 VAC vital buses.

Item 86-41 Resolve 120 VAC System SSR Problem #6

• 22.0345 (Section-3.1.6(2)) . relating to Operating Procedure A.62 (2R) enhancements.

Item 86-41-12 -

Address 120 VAC System SSR Problem #12

• 26.0356' (Section 3.1.6(3)) . relating to local indication of 120 VAC (2R) breaker status. An overview study will be done to provide a resolution of identified concerns.

Item 86-41-13 Address 480 VAC System SSR Problem #10-

• 22.0037 (Section 3.1.7(1)) relating to study of need for alarming (2R) loss of power at the MCC level. An overview study will be done to provide-a resolution of identified concerns.

~

Item 86-41-13 Resolve 480 VAC System SSR Problem #11

• 26.0298 (Section 3.1.7(2)). relating to casualty procedures (2R) enhancements.

Item 86-41-13 . Address 480 VAC System SSR Problem #16

• 26.0300 (Section 3.1.7(3)) relating to poor local indication of l(2R) certain Westinghouse MCCs. An over-view study will be done to provide a resolution of identified concerns.

Item 86-41-13 Resolve 480 VAC System SSR Problem #46

• 22.0700 (Section 3.1.7(5)) relating to a discrepancy identified in (2R) drawing E-108, Sheet 30.

Item l86-41-13~ Address 480 VAC-System SSR Problem #26

• 26.0521 (Section 3.1.7(6)) providing local indication monitoring (3R) control power on all applicable 480 V switchgear breakers. An overview study will be done to provide a resolution of identified concerns.

• Committed to in 2/12/87 ASRTP Inspection Exit Interview

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, ASRTP Inspection Response Items Committed for Resolution' Prior to Restart-

ASRTP 1R Ites # Associated QTS i (ASRTP Report Reference) Summary Item Description (QCI-12 Priority)

~

Item 86-41-13 _

Address 480 VAC System SSR Problem #19:

• 26.0338 (Section 3.1.7(7)) relating to. review.and documentation of- -(2R) 480 VAC System breaker annunciation.

~

An.

overview study will be done to provide a.

resolution of identified concerns.

' Item 86-41-14 Resolve 4160 VAC System SSR Problem #8

• 21.0248' t(Section 3.1.8(1)) relating to slotting of protective (2R) relays in the switchgear.

Item.86-41-14 Resolve 4160 VAC System SSR Problem #25'

• 22.0387 (Section 3.1.8(2)). relating to procedural enhancements for (2R)J

. monitoring DC control power to switchgear-

-breakers.

Item 86-41-14 kesolve 4160 VAC System SSR Problem #32

• 26.0965 (Saction 3.1.8(3)) relating to Operating' Procedure A.54 (2R) enhancements.

Item 86-41-14' Resolve 4160 VAC System SSR Problem #33

• 26.0966-

'(Section 3.1.8(4)) ' relating to Casualty Procedure C.143 (2R)

. enhancements.

. Item 86-41-15 Document assurance that CST relief valve 26.1083 (Section 3.2.1(2a)) .setpoints are appropriate to maintain'the (1) structural integrity of the tank (AFW SSR Problem #68).-

Item 86-41-15 Document assurance that CST vacuum. 26.1065

(Section 3.2.1(2b)) breaker protection is apprcpriate to- (1)-

maintain the structural integrity of the tank (AFW SSR Problem'#57).

Item 86-41-23 Issue revised procedure governing the 25.0162

-(Section 3.3.2) performance of safety evaluations. ~(2R)

Item 86-41-24 Issue revised procedures for site 25.0163 (Section'3.3.3)_ drawing control. (1)

. Item 86-41-24 Conduct QA audit of SDC activities to 25.0164

, (Section 3.3.3) assure compliance with approved (2R) procedures.

' # Committed to in 2/12/87 ASRTP Inspection Exit Interview

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iSRTP Inspection Response Items Committed for Resolution Prior to Restart

-ASRTP IR Item i Associated QTS f (ASRTP Report Reference) Summary Item Description, (QCI-12 Priority)

)

item 86-41-25 Submit to an evaluation of engineering 25.0092 (Section 3.3.4) . calculation practices by an independent (2R) calculation review team.

Item 86-41-25 Review study files to assure formal 25.0093 (Section 3.3.4) calculations have been prepared where (1) appropriate.

Item 86-41-26 Submit revised IST program for NRC 25.0119 ,

(Section 3.4.1(1))

approval. (1)

Item 86-41-28' Document basis for AFW minimum recircu-

• 26.1095 (Section 3.4.2(la)) lation flow valve of 60 gpm. (1)

Item 86-41-28 Establish procedure for calibration of 26.1082 (Section 3.4.2(1b)) CST level instrument LIT 35803. (1)

Item 86-41-29 Reestablish acceptable criteria for 26.1080 (Section 3.4.2(2)) stroke times of AFW control valves in (2R) accordance with ASME Section XI Article IWV requirements.

Item 86-41-30 Revise SP 210.01A to check the backseat 26.1079 (Section 3.4.2(3a)) of AFW pump discharge check valve (1)

FWS-048 (AFW SSR Problem #64).

Item 86-41-30 Revise SP 210.01A and 210.01B 26.1097 (Section 3.4.2(3b)) to specify fixed locations for (1) bearing temperature measurements of the AFW pumps.

Item 86-41-30 Revise Surveillance Procedures to 25.0180 (Section 3.4.2(3c)) specify ALERT and ACTION ranges for (2R) differential pressures and pump flows.

Item 86-41-31 Evaluate adequacy of ventilaston design 25.0106 (Section 3.4.4(1)) to maintain NSEB and AB batteries within (2R) the required design temperature ranges.

Item 86-41-31 Revise battery surveillance procedures 25.0130 (Section 3.4.4(2)) to adequately address electrolyte level, (1) specific gravity and room ambient temperature.

• Committed to in 2/12/87 ASRTP Inspection Exit Interview

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.ec ASRTP Inspection Response 1 Items Committed for Resolution Prior to Restart.

ASRTP.IR Item;f. Associated QTS #

(ASRTP Report Reference)- Summary Item Description (QCI-12 Priority)

' Item 86-41-32: Implement policy emphasizing operator 25.0165

(Section 3.5.1) attention to detail. -(2R)

- Item _86-41-33 .

Provide appropriate procedural response 25.0178 4

(Section 3.5.2(1)) ' for P-318 turbine overspeed alarm. (2R)

Item 86-41 Establish AFW pump motor' start time 26.0067-(Section 3.5.2(2)) limitations (AFW SSR Problem #20). (1)

' Item 86-41 Evaluate the. adequacy of operator 26.1066 (Section.3.5.3) procedures and training for. AFW . (2R) pump runout alarm response.

Item 86-41-36 Issue' Procedure M.115 for Dings brake 25.0132

(SectionL3.6.2(1)) -maintenance. (1)

Item 86-41-36 Establish Procedures for Air Operated 25.0131 (Section 3.6.2(2))- Valve Maintenance. (1) r Item 86-41-40 .

. Issue procedure for compliance with 25.0138

- (Section 3.7.3(1))' 10 CFR 50, Appendix B, Criterion XVI. -(1)~

Item.86-41-40 Enhance NRC Commitment Tracking per- 25.0008 (Section 3.7.3(3)) formance (See Action Plan Section 4B.11, (2R)

Commitment Management).

Item 86-41-41. Evaluate integration of LRS Management 25.0172

, - (Section'3.8.1(1)) Appraisal Report items into QCI-12 (2R) process.

. Item 86-41-42 Document measures to revalidate the 25.0173 r (Section 3.8.1(2)) adequacy of QCI-12 reviews. (2R)

Item 86-41-43. Establish controlling procedures for 25.0174 l-(Section 3.8.1(3)) '

SSR documents. Verify acceptability (2R) with NRC.

. Item 86-41-44 Implement final nuclear. organization 25.0175

' (Section 3.8.4(1)&(2)) and fill management position vacancies (1) with District employees, j

'* -Committed-to-in 2/12/87 ASRTP Inspection Exit Interview

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