ML20151D166

Summary of ACRS Reactor Operators Subcommittee Meeting on 880105 in Washington,Dc Re Inservice Testing at Nuclear Reactors

ML20151D166
Person / Time
Issue date:	02/01/1988
From:	Advisory Committee on Reactor Safeguards
To:	Advisory Committee on Reactor Safeguards
References
ACRS-2544, NUDOCS 8804130436
Download: ML20151D166 (7)

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• b l$ Z SlWARY/ MINUTES ACRS REACTOR OPERATIONS SUBCOMMITTEE, WASHINGTON, D.C.

JANt!ARY 5,1988 The ACRS Reactor Operations Subcommittee met on January 5, 1988 starting at 1:00 p.m. The purpose of the meeting was to be briefed and to discuss in-service testing at nuclear reactors. Notice of this meeting was published in the Federal Register on December 22, 1987. The meeting was open to the public except for one twelve minute session. No written or oral statements were received from members of the public. J.

Ebersole was Chairman of the Subcommittee for this session.

Principal Attendees ACRS NRC J. Ebersole, Chairman Tad March C. Michelson, Member Ted Sullivan C. Wylie, Member John Huang H. Alderman, Cognizant Staff Member Opening Statement - J. Ebersole, Chairman Mr. Ebersole noted that the current view is that valve testing is .

inadequate. Mr. Michelson added that Section XI testing has very little to do with our real concern and that is whether valves can perform their function under accident conditions.

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. Minutes / Reactor Operations Subcom. Mtg., Jan. 5, 1988 2  :

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Tad March - Mechanical Engineering Branch ,

Fr. March intrcduced Ted Sullivan and John Huang. He said that they Would like to discuss the state of Inservice Testing (IST), where things are within the NRC, our perception of problems, and our plans for resolving these problems.

Pe noted that the objective of in-service testing of pumps and valves is that together with the technical specification requirements, they ensure the operational reediness of safety relt ted pumps and valves. The technical specifications refer to in-service testing in accordance with Section XI requirer.ents.

r In-service testing is required by the regulations under 10 CFR 50.55A.

It requires that pump and valve testing programs be constructed in accordance with the ASPE code,Section XI. The regulation also raquire that IST programs be updated every ten years to the latest code and addendum. The regulations explicitly allow for relief from those regulations which are impractical an( the regulation is rot clear on wat exactly impractical means.

l Mr. Marsh n0ted three phases of testing of pumps and valves.

1. Initial acd pre-service testing. This verifies that what you have bought and installed is what you want it to be.

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, 2. Routine in-service tests and technical specification tests that verify that throughout the life of this plant that the system and the pump is able to do its intended job.

3. "As Required" tests are tests that may be done because of traintenance on pumps and valves, any special NRC initiatives, any vendor or NSSS requirements or any things not initiated by the licensee.

Mr. Marsh pointed out that ebout 30 plants have received Safety Eval-uation Reports for their in-service testing programs. He noted that many of the SER's are no longer current. He emphasized that the bulk of the plants have not received explicit reviews and safety evaluation for their in-service testing programs.

Mr. Marsh pointed out the ASME Section XI Parts lWV and IWP are regu-latory requirements by reference in 10CFR50.55A.

Mr. Michelson noted that these sections are not much help when it comes to accident or adverse loading conditions. He also remarked that these sections don't discuss maintenance procedures. such as adjustment of torque switches.

Mr. Marsh noted that plants can change their in-service testing program without the NRC explicit Safety Evaluation. The use of interim relief presents a , problem as it is very labor intensive in processing the relief requests.

liinutes/ Reactor Operations Subcom o M29., Jan. 5, 1988 4 John Huang - Mechanical Engineering Branch Mr. Huang discussed the review process. The first part of the review is to make sure that all safety related components are cnvered in the program. The second part is to make sure that all of the required tests are perforred correctly in accordance with ASME Section XI requirements.

In the second part of the review, if the licensee cannot meet the testing requirements as specified in the code, they will submit reouests for relief and sometimes they may propose alternative tests so the reviewer can review the adequacy and acceptability of those relief requests and/or alternative test rethods.

The subcomittee discussed the flow testing requirements for pumps. It was established that pumps are tested at one flow rate only, not a spectrun of flow rates.

Mr. Huang remarked that following the review, they usually develop a set of requests for additional informatien that is sent to the licensee for response. The licensee is allowed 60 to 90 days to respond. Following the response, the Staff meets with the licensee to resolve all the open issues. Following the meeting, the licensee usually develops a satis-factory revised IST program. After the licensees resubmittal, the Staff will most likely concur and issue the Safety Evaluation Report.  ;

Mr. Huang next oiscussed Section XI requirements for pumps. He noted that the in'let pressure is measured. The discharge pressure is then

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Minutes / Reactor Operations Subcom c Mtgo, Jan. 5, 1988 5 measured. Then the differential pressure across the pump is calculated and the flow rate is measured. The vibration of the pump is measured and the vibration amplitude. The lubricant level is verified and the bearing temperature is measured.

Mr. Huang rentioned valve testing. The valves are exercised to check opening and closing. He noted there are certain valves that require both exercising and stroke timing. Certain safety related valves also require leak testing.

Fail safe valves are tested to ensure that they fail safe. Safety relief valves are tested to verify the set-p int pressure.

Ted Sullivar, Mechanical Engineerino Branch Mr. Sullivan discussed problem areas. The first area he noted was inefficient or deficient testing requirements in the code. Another problem is the lack of implementation guidance. Mr. Fichelson pointed out lack of guidance by the NRC on what tests should have been initially performed.

l Mr. Sullivan mentioned legal problems. These center nainly around the regulatory requirements and in what time frame relief requests should be granted. The question of practicality falls under this umbrella. The code states that relief may be granted where testing is impractical.

What is inpractical can be disputed.

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• Mr. Marsh noted some questions that the NRC is asking themselves regard- ,

ing policy and procedures:

o Decause of the problem with the ASME code, should the NRC continue to rely on Section XI or the 0 and M to develop pump and valve IST standards?

• o Should the NRC require prior written approval for relief requests?

o To what extent should update to a later code version be required?

o Should the NRC IST efforts be more inspection oriented and less program and relief request review oriented?

o Should licensees be allcred to modify and implement IST program revisions without NRC review?

2 Mr. Marsh talked about the INPO check valve effort. He said the NRC had requested INP0 to take the lead on check valves. Mr. Page stated that ,

INPO is about to publish a "very thick" application guide on check valve applicetions and check valve designs.

Mr. Marsh talked about industry initiatives, one of which is to improve i the code or in-service testing to include more neaningful and

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, technically defensable testing. They could form owners groups to address generic problems with IST.

Mr. Marsh noted that their focal point for change is the code Committee.

He added that within NRC the focal point for pumps and valves is within the Mechanical Engineering Branch of NRR.  ;

In response to a question as to how the ACRS can support this effort Mr.

Marsh replied that the Subcommittee could report to the full Committee that you endorse the work the Staff is doing and you would like to hear more about it. He also noted the ACRS could recommend industry initia-tives.

The meeting was adjourned at 4:48 p.m. -

NOTE: Additional meeting details can be obtained from a transcript of this meeting available in the NRC Public Document Room, l 1717 H St., NW., Washington, D.C. or can be purchased from Heritage Reporting Corporation, 1220 L Street, NW., l Washington, D.C. 20005,(202)628-4888. . ;

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