ML20246F467

Safety Evaluation Re Inservice Testing Program & Requests for Relief Re ASME Class 1,2 & 3 Pumps & Valves.Program Acceptable

ML20246F467
Person / Time
Site:	Rancho Seco
Issue date:	05/04/1989
From:	Office of Nuclear Reactor Regulation
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ML20246F466	List: ML20246F463 ML20246F467 ML20246F473
References
NUDOCS 8905120257
Download: ML20246F467 (8)

Text

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ENCLOSURE 1 i

SAFETY EVALUATION REPORT BY OFFICE OF NUCLEAR REACTOR REGULATION J

RELATED TO THE INSERVICE TESTING PROGRAM AND REQUESTS FOR RELIEF SACRAMENTO MUNICIPAL UTILITY DISTRICT RANCHO SECO NUCLEAR STATION DOCKET NO.: 50-312 INTRODUCTION I

The Code of Federal Regulations,10 CFR 50.55a(g), requires that inservice testing (IST) of ASME Code Class 1, 2, and 3 pumps and valves be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable. addenda, except where specific written relief has been requested by the licensee and granted by the Commission pursuant to 10 CFR 50.55a(a)(3), or (g)(6)(i).

In requesting relief under 10 CFR 50.55a(a)(3)(i) or (g)(6)(i), the licensee must demonstrate that:

(1) the proposed alternatives provide an acceptable level of quality and

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safety or (2) the conformance with certain requirements of the applicable Code edition and addenda is impractical for its facility.

The Regulation, 10 CFR 50.55a(a)(3)(i), and (g)(6)(i), authorizes the Commission to grant relief from these requirements upon E king the necessary findings.

The NRC staff's findings with respect to granting or not granting the relief requested as part of the licensee's IST Program are contained in the Safety Evaluation (SE) issued on the licensee's program.

The IST Program addressed in this report covers the second ten year inspection interval from April 17, 1985 to April 17, 1995.

The licensee's program is described in a letter dated January 28, 1988, which supersedes all previous sub-l mittals.

Additional information was submitted in a letter dated February 15, 1988.

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The program is based on the requirements of Section XI of the ASME Code, 1980

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Edition through the Winter of 1981 Addenda.

EVALUATION The IST Program and the requests for relief from the requirements of Section XI have been reviewed by the staff with the assistance of its contractor, EG&G, Idaho, Inc. (EG&G).

In addition, EG&G and staff members met with licensee representatives on January 6 and 7, 1988, in a working session to discuss questions resulting from the review.

The Technical Evaluation Report (TER)

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provided as Attachment 1 is EG&G's evaluation of the licensee's inservice testing progr6m and relief requests.

The staff has reviewed the TER and concurs with, and adopts, the evaluations and conclusions contained in the TER.

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A summary of the pump and valve relief request determinations is presented in Table 1.

The granting of relief is based upon the fulfillment of any commitments made by the licensee in its basis for each relief request and the alternative proposed testing.

Two relief requests were denied (TER Sections 3.2.2, and 4.1.3.1) and eight relief requests were granted with certain conditions (TER Sections 3.3.1, 3.2.6, 4.1.2.1, 4.4.2.1, 4.4.3.1, 4.5.1.2, 4.5.1.1, and 4.8.2.1).

The licensee should

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f refer to the specific TER section for a detailed discussion of these cases.

These J

denials and conditions are listed in the TER Appendix C and in addition, Appendix C lists other IST Program anomalies which were identified during a review.

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1 The licensee should resolve all the items listed in Appendix C in accordance with the staff positions.

Required program changes should be made within 90 days of receipts of this SER.

CONCLUSION Based on the review of the licensee's IST Program and relief requests, the staff concludes that the IST Program as evaluated and modified by this SER will provide reasonable assurance of the operational readiness of the pumps and valves covered by the IST Program to perform their safety related functions.

The staff has determined that granting relief, pursuant to 10 CFR 50.55a(a)(3)(i), and (g)(6)(i),

is authorized by law and will not endanger life or property, or the common defense and security and is otherwise in the public interest.

In making this determination

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the staff has considered the alternate testing being implemented, or the imprac-ticality of performing the required testing considering the burden if the require-ments were imposed.

The last column of Table 1 identifies the regulation under which the requested relief is granted.

During the review of the licensee's inservice testing program, the staff has identified certain misinterpretations or omissions of Code requirements.

These items are summarized in the TER Appendix C.

The IST Program for Rancho Seco through revisions identified in a letter to the staff dated January 28, 1988, is acceptable for implementation provided that the items noted above are corrected promptly.

Relief requests contained in any subsequent revisions may not be implemented without prior approval by NRC.

Y RANCHO SECO NUCLEAR GENERAT8NG STATION

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p SER TABLE 1-

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SUMMARY

OF' RELIEF REQUESTS

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RELIEF TER SECTION XI EQUIPMENT ALTERNATE ACTION-i REQUEST SECTION REQUIREMENT IDENTIFICATION METHOD OF BY-NUMBER

& SUBJECT-TESTING USNRC

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i Pump 3 '. 2.1 NP-3110 All pumps in Measure pump' flow Relief PR-l' feference

program, rate and Granted.

differential differential (g)(6)(1) pressure.

pressure and compare to pump curve.

Pump 3.3.1 IWP-4510 All pumps in Optionally measure Relief PR-2 Vibration

program, vibration velocity Granted displacement in two locations.

provided and measurements measurement taken as location.

discussed in

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TER section.

3.3.1.

(a)(3)(i)

Pump 3.1.2 IWP-4120 Full All pumps in Utilize digital Relief PR-3 scale range program.

vibration Granted.

requirement.

instrumentation.

(g)(6)(i)

Pump 3.2.2 IWP-3100-2 All pumps in Increase Alert Range Aeiief PR-4 Alert and program.

(high) to Denied.

Required 105%, increase Action Range Required Action (high)

Range (high) to limits.

>110% for flow rate and delta pressure.

Pump 3.3.3 IWP-3100-1 All pumps in None.

Relief PR-5 Bearing program.

Granted, temperature (g)(6)(i) measurement.

Pump 3.2.3 IWP-3100-1 All pumps in Measure pump inlet Relief PR-6 Inlet program.

pressure only during Granted.

pressure pump operation.

(g)(6)(1) measurement.

Pump 3.2.4 IWP-3100-1 P-236, P-23BA Measure all Relief PR-7 Flow rate and P-2388.

parameters during

Granted, measurement.

refueling outage (g)(6)(i) full flow test.

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RANCHO SECO NUCLEAR GENERATfNG STATION SER TABLE 1

SUMMARY

OF RELIEF REQUESTS RELIEF TER SECTION XI EQUIPMENT ALTERNATE ACTION REQUEST SECTION REQUIREMENT IDENTIFICATION METHOD OF BY NUMBER

& SUBJECT TESTING USNRC Pump 3.2.5 IWP-3100-1 P-472A & 8, Measure pump suction Relief PR-8 Inlet P-108A-D, and fluid height once

Granted, pressure P-888A-D.

during pump test.

(g)(6)(i) measurement.

Pump 3.2.6 IWP-3100-1 P-472A, For pumps P-472 Interim PR-10 Flow rate P-472B, calculate flow rate Relief measurement.

P-482A, and from system flow Granted P-4828.

curve.

None for until pumps P-482.

completion of Refueling Outage No.

7. (g)(6)(i)

Pump 3.1.1 IWP-4120 Full P-236, P-238A Utilize installed Relief PR-11 scale range

& B, P-261A & suction pressure Granted.

requirement.

B, P-291A & B, instrumentation.

(g)(6)(i) and P-705A &

B.

pump 3.2.7 IWP-3500(a)

P-108A-D and Calculate flow rate Relief PR-13 Pump test run P-888A-D.

with day tank level Granted.

time,1WP-4600 change over time.

(g)(6)(i)

Flow rate Take test data when meter.

flow and pressure stabilized.

Pump 3.3.2 IWP-4510 P-108A-D and None.

Relief PR-14 Vibration P-888A-D.

Granted, measurement.

(g)(6)(i)

Pump 3.4.1 IWP-3230(a)

P-888A-0.

None.

Relief PR-15 Corrective Granted.

action (g)(6)(i) requirements.

Valve 4.1.2.1 IWV-3417 TV-1, TV-2, Verify stroke time Relief VR-1 Corrective TV-3, TV-4, for rapid acting Granted in Action.

and rapid valves as less than accordance acting 2 seconds, declare with solenoid inoperable if stroke discussion valves.

time exceeds 2 in TER l

seconds.

Section 1

4.1.2.1.2.

(g)(6)(1)

(page Zo.

3 RANCHO SECO NUCLEAR GENERATING STATION SER TABLE 1

SUMMARY

OF RELIEF REQUESTS RELIEF TER SECTION XI EQUIPMENT ALTERNATE ACTION REQUEST SECTION REQUIREMENT IDENTIFICATION METHOD -OF BY NUMBER

& SUBJECT TESTING USNRC Valve 4.1.3.1 IWV-3417(a)

Cold shutdown Delete increased Relief VR-2 Corrective exercised test frequency, if Denied.

Action.

power operated degraded valve is valves.

operable.

Valve 4.1.4.1 1WV-3420 Leak Containment 10 CFR 50, Appendix Relief VR-4 rate testing. isolation J and IWV-3426 and Granted.

valves.

IWV-3427.

(a)(3)(i)

Valve 4.2.2.1 IWV-3521 Test RIVVWX, Full-stroke exercise Relief VR-5 frequency.

RIVVWZ, during refueling Granted.

RIVVXW, outages.

(g)(6)(i)

RIVVXY, RIVVYX,

RIVVYZ, RIVVZW, and RIVVZY.

Valve 4.3.1.2 IWV-3521 Test BWS-019, Full-stroke exercise felief VR-6 frequency.

BWS-044, during refueling Granted.

SIM-043, and outages.

(g)(6)(i)

SIM-052.

Valve 4.3.1.3 IWV-3521 Test SIM-002, Full-stroke exercise Relief VR-7 frequency.

SIM-045, and during refueling Granted.

SIM-058.

outages.

(g)(6)(i)

Valve 4.3.2.1 IWV-3521 Test HV-23801, Full-stroke exercise Relief VR-8 frequency.

SIM-036, during refueling Granted.

SIM-040, and outages.

SIM-036 (g)(6)(i)

SIM-047.

closure verification during cold shutdowns.

Valve 4.3.1.1 IWV-3521 Test SIM-037, Full-stroke exercise Relief VR-8 frequency.

SIM-041, during refueling Granted.

SIM-049, and outages.

(g)(6)(i)

SIM-050.

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Valve 4.4.3.2 IWV-3427(b)

CFS-001, Leak rate testing in Relief VR-9 Leak rate CFS-002, accordance with

Granted, evaluation.

DHS-015, Technical (a)(3)(i)

DHS-016, Specifications Table F'CS-001, and 3.3-1.

RCS-002.

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RANCHO SECO NUCLEAR GENERATING STATION f

SER TABLE 1 i

SUMMARY

OF RELIEF REQUESTS RELIEF TER SECTION XI EQUIPMENT ALTERNATE ACTION REQUEST SECTION REQUIREMENT IDENTIFICATION METHOD OF BY

).

NUMBER

& SUBJECT TESTING USNRC Valve 4.4.2.2 IWV-3521 Test BWS-045.

Full-stroke exercise Relief VR-10 frequency.

during refueling Granted.

outages.

(g)(6)(i)

Valve 4.4.3.1 IWV-3522 CFS-001 and Partial-stroke Relief VR-11 Full-stroke CFS-002.

exercise during cold Granted in exercise.

shutdowns.

accordance Disassemble / inspect with one valve only discussion during Refueling in TER Outage No. 7.

Section 4.4.2.1.2.

(g)(6)(i)

Valve 4.4.2.1 IWV-3522 CBS-035 and Sample Relief VR-13 Full-stroke CBS-036.

disassembly /inspec-Granted in exercise.

tion / manual accordance full-stroke with I

exercising during

- discussion refueling outages.

in TER Section 4.4.2.1.2.

(g)(6)(i) j Valve 4.5.1.2 IWV-3522 CBS-009 and Sample Relief VR-14 Full-stroke CBS-010.

disassembly /inspec-Granted in exercise.

tion / manual accordance full-stroke with exercising during discussion refueling outages, in TER Section 4.4.2.1.2.

1 (g)(6)(i)

Valve 4.5.1.1 IWV-3522 CBS-021, Sample Relief VR-15 Full-stroke CBS-022, disassembly /inspec-Granted in exercise.

CBS-027, tion / manual accordance j

CBS-028, full-stroke with l

SFV-29015, and exercising during discussion l

SFV-29016.

refueling outages.

in TER l

Section 4.4.2.1.2.

l (g)(6)(i)

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RANCHO SECO NUCLEAR GENERATING STATION l

SER TABLE 1

SUMMARY

OF RELIEF REQUESTS I

RELIEF TER SECTION XI EQUIPMENT ALTERNATE ACTION REQUEST SECTION REQUIREMENT IDENTIFICATION METHOD OF BY NUMBER

& SUBJECT TESTING USNRC Valve 4.1.1.1 IWV-3510 All Test safety and Relief VR-16 Safety and safety / relief relief valves in Granted.

relief valve valves in accordance with (a)(3)(i).

testing.

program.

ANSI /ASME OM-1-1981.

Valve 4.6.1.1 IWV-3521 Test FWS-049 and Full-stroke' exercise Relief VR-17 frequency.

FWS-050.

during refueling Granted.

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outages.

(g)(6)(i)

Valve 4.7.1.1 IWV-3423 Leak SFV-60001 and Test pressure Relief

(

VR-19 rate testing. SFV-60003.

applied downstream Granted.

of valve.

(a)(3)(1)

Valve 4.4.1.1 IWV-3423 Leak HV-26515 and Test pressure Relief VR-20 rate testing. HV-26516.

applied downstream Granted.

of valve.

(g)(6)(i)

Valve 4.8.3.1 IWV-3413 Diesel Monitor proper Relief VR-21 Stroke time generator air startup of diesel 4 ranted.

measurement.

start solenoid generator.

(g)(6)(i) i valves.

Valve 4.2.1.1 IWV-3412 PSV-21511.

Functionally test at Relief VR-22 Full-stroke cold shutdown.

Granted.

exercise.

Bench test during (g)(6)(1) refueling outages.

Valve 4.8.2.1 IWV-3522 EGS-564, Sample Relief

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VR-23 Full-stroke EGS-565, disassembly /inspec-Granted in exercise.

EGS-566, and tion / manual accordance EGS-567.

full-stroke with j

exercising during discussion refueling outages.

in TER Section 4.4.2.1.2.

(g)(6)(i)

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