ML20237A568

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Forwards Supplemental Response to Technical Evaluation Rept Re Items 3.3.5, Containment Isolation Valve Position & 3.3.11, Accumulator Tank Level & Pressure, Concerning Application of Reg Guide 1.97 at Plant
ML20237A568
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 12/08/1987
From: Leblond P
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 3916K, GL-82-33, TAC-51367, TAC-51368, NUDOCS 8712150101
Download: ML20237A568 (16)


Text

__-_ _________

e Ctmm:nwr.Ith Edison 2

V One First National Plaza. Chicago Ittinois Kddress Feply to: Post Offce Box 767 Chicago, Illinois 60690 0767 December 8, 1987 l

l U.S. Nuclear Regulatory Commission Attn: Document control Desk Washington, DC 20555

Subject:

Zion Nuclear Power Station Units 1 and 2 NUREG - 0737, Supplement 1 - Confirmatory Order Regulatory Guide 1.97 NRC Docket Nos. 50-295 and 50-304 TAC Nos. 51367/8 _

References (a): June 12, 1984 letter from S.A. Varga to D.L. Farrar (b): August 1, 1986 letter from P.C. LeBlond to H.R. Denton (c): May 15, 1987 letter from D.R. Muller to D.L. Farrar (d): August 24, 1987 letter from P.C. LeBlond to US NRC Gentlemen:

This transmittal is providing the NRC Staff with the results of additional review regarding the application o. Regulatory Guide 1.97 at Zion Station. Reference (a) transmitted an order confirming Commonwealth Edison company's commitment made in response to Generic Letter 82-33. Included among these items was a commitment to submit a preliminary report describing l how the requirements of Regulatory Guide 1.97 have been or will be met at Zion Station. That report was submitted in reference (b).

Reference (c) provided Commonwealth Edison Company with an interim Technical Evaluation Report (TER) and requested a response regarding the twenty-two open items identified in the TER. Commonwealth Edison Company's review of twenty of these open items was contained in reference (d).

Reference (d) stated that two items would require additional study. These items were:

3.3.5 - Containment Isolation Valve Position 3.3.11 - Accumulator Tank Level and Pressure commonwealth Edison Company has completed this additional study.

The results of this work are contained in the Attachment to this letter, go) 8712150101 871200 PDR ADOCK 05000295 \

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US NRC December 8, 1987 In addition, an internal Commonwealth Edison Company technical review has identified a concern regarding TER item 3.3.26. Reference (d) stated that "The existing flow instrumentation, FT-PR53, is capable of measuring flow in the range of 0 to 229,500 CFM".

This technical review has questioned the accuracy of the flow ]j instrumentation in the lower ranges (less than approximately 20,000 CFM).

l As a result, the adequacy of FT-PR53 is being reexamined. Commonwealth Edison expects to notify the NRC Staff of the results of this rereview by March 1, 1988. j

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If any further questions arise regarding this matter, please direct l them to this office. l Very truly yours, Ph 4 P. C. LeBlond i Nuclear Licensing Administrator l 1

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Attachment cc: Resident Inspector - Zion l J. A. Norris - NRR i

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l ATTACHMENT SUPPLEMENTAL RESPCNSE TER ITEMS; l

3.3.5 and 3.3.11  !

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3.3.5 Containment Isolation Valve Position (Variable 29)  !

l Regulatory Guide 1.97 recommends Category 1 valve position indication j for the purpose of verifying the accomplishment of isolation. The i licensee has provided a list of containment isolation valves and  !

justification for exceptions (note 26) from the regulatory guide recommendations.

Based on the information provided, we are unable to determine that the recommendations for (a) redundancy, (b) single-failure criterion and )

(c) environmental qualification have been met.  !

a. The licensee has listed a group of valves that do not have position indication for series pairs. The licensee states that backup ,

indication is provided by various plant system variables. The I licensee should provide additional information for the valves listed i.e., why is there no indication of individual valves of the series pair? Why is a plant system variable adequate to determine the proper valve position?

b. The licensee states that all air operated and solenoid operated valves fail in the safe direction (closed) on loss of power, thus, position status for these valves need only meet Category 3 criteria.

The fact that these valv(s are supposed to fail shut is not i sufficient justification for not meeting the single failure criterion. In an accident situation, the operator should be able to ascertain that the valves are in fact shut from the position j indication. The licensee should meet this single failure criterion. j

c. We are unable to determine from the licensee's submittal which valve position switches are located in a mild environment and which l ones are not. The licensee should provide information that j verifies that all valve position switches requiring environmental  !

qualification do in fact have the proper switch.

Ceco Response:

J Regulatory Guide 1.97 Rev. 2 indicates that Category 1 instrumentation I is recommended for those key variables >51ch monitor accident  !

conditions. Containment isolation valva position indication is used by l the operator to detertine accomplishme it of a safety function, not to monitor accident conditions. The Catecary 1 variables required to monitor accident conditions which could cause a breach of containment were determined based on Section 1.2 of Regulatory Guide 1.97 which states in part:

"The sources of potential breach are limited to the energy sources within the cladding, coolant boundary, or containment."

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The key variables which are used to monitor accidents which may produce

" energy sources within ... containment" are:

  • Containment pressure Containment Radiation j Because containment isolation valve position indication is not the i primary indication of the above variables, it was re-classified as a Category 2 variable. The following additional justification is l provided for the Category 2 classification:
  • Containment isolation valve position indication does not provide  !

the operator with information required to monitor containment conditions during or post-accident.

  • Containment isolation valve position indication information is not used to prevent or mitigate adverse containment conditions.  ;

The containment isolation function is a result of adverse containment conditions. Since the containment isolation function 1s interlocked to the key variables indicating accident and/or adverse containment conditions, it can be used as back-up indication of adverse containment conditions. Containment pressure and radiation monitoring instruments are designated as Category 1 instrumentation.

Containment isolation valve position indications are used to determine the status of each valve. Regulatory Guide 1.97 Rev. 2 page 3 states that Category 2 " generally applies to instrumentation designated for indicating system status". This is consistent with determination of valva status, i.e. open or closed.

A revised listing of conta!nment isolation valves is shown on Table 3, attached. With the except2on of manual valves, Table 3 shows each containment isolation valve listed in Section 3.9 of the Zion Station Technical Specification as updated by Amendments 95 and 105 effective June 23, 1987. Responses to NRC Technical Evaluation Report Item 3.3.5 were formulated to address this revised listing.

a. Redundancy j Regulatory Guide 1.97 Rev. 2 does not require Category 2 variables to meet single-failure criteria. Since redundancy is used as a means of meeting single-failure criteria, redundant containment isolation valve position indication is not required. However, it should be noted that i most containment isolation valve position indications at Zion Station are redundant.

Table 3 shows the series pair valve associated with each containment isolation valve listed. Each containment isolation valve and its series pair valve are equipped with independent individual position indication except as noted. As noted on Table 3, a number of series pair valves are check valves. Table 2 of Regulatory Guide 1.97 Rev. 2 specifically excludes check valves from requiring position j '

indication. Therefore, all of the containment isolation valves listed

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f with series pair valves have redundant position indication and therefore meet single-failure criteria. For those valves which do not have a series pair valve, the following justification is provided:

A0V-CC9437 is a component cooling system containment isolation valve. The component cooling system piping isolated by AOV-CC9437 is a closed loop system. In order for a breach of containment to cause a release of radioactive materials, a simultaneous breach in ,

the component cooling pressure boundary and failure of the l containment isolation valve must occur. Also, A0V-CC9437 is a j normally closed, fail-closed valve allowing the operator to I ascertain the correct valve position in the event of a failure of the position indication.  ;

i

  • PCV-FP08 provides containment isolation for the fire protection I system. This valve is a normally closed, fail-closed valve, allowing the operator to ascertain the correct valve position.
  • FCV-SS02, 3, 4 & 5 provide isolation of the steam generator blowdown sampling lines. Each of the four lines is a 3/8-inch diameter sample line routed to the steam generator sample panel and i sink. Failure of the isolation valves alone will not cause a breach of containment resulting in a radioactive release. Because blowdown sampling is a secondary system, a simultaneous failure of the primary system pressure boundary, (steam generator tubes), and the containment isolation valves must occur to initiate a radioactive release. Since these sample lines are equipped with radiation detection instrumentation, this instrumentation, RR-0001, j can be used as back-up instrumentation to determine if a breach of containment which could result in a release of radiation exists.
  • Main steam isolation valves HOV-MS0001, 2, 3 and 4 and MSIV bypass valves FCV-MS82, 83, 84 and 85. Redundancy for these valves is provided by the flow, pressure, and radiatior. instrumentation associated with main steam flow. This additional instrumentation was previously identified as meeting Regulatory Guide 1.97 Rev. 2 recommendations for Category 2 variables. The pressure, flow and radiation instrumentation available for back-up indication of valve closure were listed in the original Zion Station Regulatory Guide 1.97 submittal as variable numbers 62, 63, and 86 respectively.
  • MOV-SW0001, 2, 7, 8, 9, 10 & 11 are the service water isolation valves. The s<rtice water system in containment consists of a closed loop c Jing water system for the containment ventilation coolers. The discharge lines are equipped with radiation detection instrumentation. These instruments provide monitoring for radioactive materials which could be transported in the service water system following a breach in the closed loop system and failure of the containment isolation valves.

Since the purpose of the containment isolation function is to prevent the release of radioactive materials from containment, the existing valve position indication together with the radiation monitoring equipment (pR014 & RRPR19) provide sufficient redundancy to determine if a breach of containment exists.

l

b. Single-Failure Criteria Category 2 variables are not required to meet single-failure l criteria. However, in order to address the NRC concerns the following response was prepared.

The containment isolation valves with series pair valves are redundant and therefore satisfy single-failure criteria. This is because the series pair containment isolation valves have physically separate individual position indications (excluding check valves).

With the exception of A0V-CC9437 and FCV-PP08, the A0V's and FCV's without series pair isolation valves are equipped with redundant separately powered control air solenoids. This ensures that a single-failure will not prevent accomplishment of containment isolation since these valves are fail-closed.

Single-failure criteria for the MSIV's, MSIV bypass, and service water  ;

isolation valves is met by the back-up instrumentation discussed above.

c. Environmental Qualification Table 3 shows the zone and environment for each containment isolation valve. Valves located in mild environments and qualified motor operated valves with internal limit switches, meet Regulatory Guide 1.97 environmental qualification recommendations.  ;

i The majority of the remaining valves are in " radiation only" environments. The position switches for these valves as well as all other containment isolation valve position switches will be analyzed to confirm their suitability for their environments. Those position switches which do not meet the standards required for reliable ]

operation in their respective environments will be replaced on an j "as-fail" basis as part of normal maintenance activities. Replacement switches will be selected in accordance with Regulatory Guide 1.97 environmental qualification recommendations, i

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3.3.11 Accumulator Tank Level and Pressure Regulatory Guide 1.97 recommends environmentally qualified instrumentation for this variable with a range of 10 to 90 percent volume (for level) and 0 to 750 psig (pressure). The licensee has supplied instrumentation with no environmental qualification. The provided ranges are approximately 20 to 95 percent of the tank volume and 0 to 700 psig.

The licensee states that the primary function of both level and pressure instrumentation is to monitor the pre-accident status of the accumulator tanks to assure that this passive safety system is prepared to serve its safety function.

The accumulators are passive devices. Their discharge into the reactor coolant system (RCS) is actuated solely by a decrease in RCS pressure. We find that the ranges of the instrumentation supplied for this variable are adequate to determine that the accumulators have discharged.

Therefore, the ranges of this instrumentation are acceptable for this variable.

The existing non-qualified instrumentation is not acceptable. An environmentally qualified instrument is necessary to monitor the status of these tanks. The licensee should designate either level or pressure as the key variable to directly indicate accumulator discharge and provide instrumentation for that variable that meets the requirements of 10 CFR 50.49 and Regulatory Guide 1.97.

In response to reference (c) CECO has performed a detailed review of Emergency Operating procedures as they relate to the use of accumulator Tank Level and pressure Instrumentation, item 3.3.11 of the TER. We have determined that neither accumulator tank level nor pressure instrumentation is used anywhere in the EOp's. Based up.on this information, there is sufficient additional justification to tbclassify the subject instrumentation as Category 3. Listed below is the summary of that review.

1. E-O Reactor Trip or Safety Iniection This procedure verifies that the auto actions were performed and attempts to diagnose the accident. - No mention is made of accumulator tank level or pressure instrumentation.
2. .E- 1 Loss _.of Reactor __or Secondary Coolant This procedure continues to verify and diagnose the accident and confirm E-O diagnostics. If large LOCA exists, subprocedure ES-1,3 is utilized; subprocedure ES-1.2 for small LOCA. - Again, no mention is made of accumulator tank level or pressure l instrumentation.

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3. ECA-0.0 Loss of All AC Power With loss of all AC power the ability of supplying any cooling water is lost. RCP seals are postulated to leak, leading eventually to large LOCA. - No direction is given for the operator to verify the injection of the accumulators, or to check accumulator tank level or pressure.

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4. ECA-1.1 Loss of Emergency Coolant Recirculation j l

This procedure addresses the existence of a LOCA combined with an  !

inability to go to cold leg recirculation. Actions are taken to maximize make-up and reduce the outflow. Core Exit T/C's and RVLIS are used to determine adequate core cooling. - Accumulator tank level or pressure instrumentation is not used here at all. l S. FR-C.1 Response to Inadequate Core Coolin_g FR-C.2 Response to Degraded Core Cooling l

Reactor coolant system pressure, temperature and RVLIS are {

primarily relied on in these procedures. - Again, the accumulator l tank level or pressure are not required.

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