ML20211J981

Application for Amends to Licenses NPF-41 & NPF-51,revising Tech Specs to Reflect Current Organization & Allow Testing of Charcoal Filter Units Per ANSI N509-1980.Fee Paid

ML20211J981
Person / Time
Site:	Palo Verde
Issue date:	11/06/1986
From:	Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Knighton G Office of Nuclear Reactor Regulation
Shared Package
ML17300A622	List: ML20211J981
References
ANPP-38963-JGH, TAC-64071, TAC-64072, NUDOCS 8611130323
Download: ML20211J981 (18)

Text

. .

Arizona Nuclear Power Project P O Box 52034

• PHOENIX. ARIZONA 85072-2034 November 6, 1986 ANPP-38963-JGH/JRP/98.05 Director of Nuclear Reactor Regulation Attention: Mr. George W. Knighton, Project Director PWR Project Directorate #7 Division of Pressurized Water Reactor Licensing - B U. S. Nuclear Regulatory Commissio Washington, D. C. 20555

Subject:

Palo Verde Nuclear .;enerating Station (PVNGS)

Units 1 and 2 Docket Nos. STN 50-528 (License NPF-41)

STN 50-529 (License NPF-51)

Technical Specification Change File: 86-005.419.05; 86-056-026

Dear Mr. Knighton:

This letter is provided to request two changes to the PVNGS Units 1 and 2 Tech-nical Specifications. The request consists of the following proposed changes:

Specification Section 6; Administrative Controls, Figures 6.2-1 and 6.2-2.

The proposed change would revise the subject figures to represent the cur-rent organization. This change is necessary because Palo Verde is shift-ing its emphasis from the construction phase to a commercial operation phase.

Specification Sections 4.6.4.3.b.2, 4.6.4.3.C, 4.7.8.b.2, 4.7.8.C, 4.9.12.b.2 and 4.9.12.C, surveillance requirements for the Essential Filtra-tion System. The proposed change will allow testing of the charcoal filter units in accordance with ANSI N509-1980 in lieu of the currently required ANSI N509-1976. This standard has been accepted by the NRC and the accep-tance is documented in Section 6.5.1 of the standard Review Plan, Revision 2, July 1981 (NUREG-0800).

Enclosed within these change requests-are:

A. Description of the Proposed Change Request B. Basis for No Significant Hazards Determination C. Safety Analysis of the Proposed Change Request D. Environmental Impact Consideration Determination E. Marked-up Technical Specification Change Pages

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Mr. George Knighton Technical Specification Change Page 2 ANPP-38963 Pursuant to 10 CFR 50.91(b)(1), and by a copy of this letter and attachments, we have notified the Arizona Radiation Regulatory Agency of this request for a Technical Specification change. In accordance with 10 CFR 170.12(c), the license amendment application fee of $150 is also enclosed.

Very truly yours, d@

J. G. Ilaynes Vice President Nuclear Production JGil/JRP/1s Attachments cc: 0. M. DeMichele E. E. Van Brunt Director Region V USNRC NRC Project Manager- E. A. Licitra (w/a)

NRC Resident Inspector- R. P. Zimmerman Director ARRA- C. F. Tedford (w/a)

A. C. Gehr

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SECTION 6 ADMINISTRATIVE CONTROLS i

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N I A. DESCRIPTION OF AMENDMENT REQUEST The proposed amendment would ' modify Section 6, Figures 6.2-1 and 6.2-2 to

represent the current organization. The Executive Vice President of Arizona Nuclear Power Project will be reporting to the President and Chief Operating 4

Officer of Arizona Public Service Company. Previously, the Executive Vice President reported directly to the Chief Executive Officer. This change was made because Palo Verde is shifting from its construction phase to its commercial operation phase.

Additional changes can also be seen on these figures in that: (1) the Compliance Department will report to the plant manager. This change is intended to increase the effectiveness of compliance in responding to regulatory and plant issues. And, (2) the title of Figure 6.2-2, has been l changed from "0NSITE UNIT ORGANIZATION" to "0NSITE ORGANIZATION".

B. BASIS FOR NO SIGNIFICANT HAZARDS DETERMINATION (A) The proposed change does not involve a significant hazards consideration i because operation of Palo Verde Units 1 and 2, in accordance with thia l change would not:

(1) Involve a significant increase in the probability or consequences of an accident previously evaluated.

The changes in the organization will in no way affect the safety of i the plant, in that the President of APS has the overall authority for electric . operations and PVNGS is shifting its emphasis to an operational phase.

(2) Create the possibility of a new or different kind of accident from any previously analyzed. It has been determined that a new or different kind of accident will not be possible due to this change because the changes made to the organization are administrative in j nature and do not affect the operation of PVNGS.

(3) Involve a significant reduction in a margin of safety. The margin

, of safety will not. be reduced, the proposed changes in the organization reflect an operational approach to Palo Verde.

(B) The Commission has provided guidance concerning tne application of the standards for determining whether a significant hazards consideration exists. The proposed change is similar to example (ix), other: an administrative change to reflect a change in the existing organization.

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C. SAFETY ANALYSIS OF THE PROPOSED CHANGE REQUEST The proposed technical specification change will not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the FSAR. This change is an administrative change to the organization charts, it has no affect on plant operaticn.

The proposed technical specification change will not create the possibility for an accident or malfunction of a different type than any evaluated previously in the FSAR. No physical changes are being made to the plant, the changes presented here only affect the organization and are administrative in nature.

The proposed technical specification change will not reduce the margin of l safety as defined in the basis for any technical specification. The change in l the organization reflects an operational approach to Palo Verde and has no affect on the margin of safety. l D. ENVIRONMENTAL IMPACT CONSIDERATION DETERMINATION The proposed change request does not involve an unreviewed environmental question because operation of PVNGS Units 1 and 2 in accordance with this change would not:

(1) Result in a significant increase in any adverse environmental impact previously evaluated in the Final Environmental Statement (FES) as modified by the Staff's testimony to the Atomic Safety and Licensing Board, Supplements to the FES, Environmental Impact Appraisals, or in any decesions of the Atomic Safety and Licensing Board; or (2) Result in a significant change in effluents or power levels; or (3) Result in matters not previously reviewed in the licensing basis for PVNGS which may have a significant environmental impact.

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O 3/4 6.4 COMBUSTIBLE GAS CONTROL 3/4 7.8 ESF PUMP ROOM EXHAUST CLEANUP SYSTEM 3/4 9.12 FUEL BUILDING ESSENTIAL VENTILATION SYSTDI

A. DESCRIPTION OF THE PROPOSED CHANGE REQUEST The requested change regarding the ESF air filtration unit charcoal involves only the initial qualification tests which are performed by the manufacturers to certify suitability of the impregnated activiated carbon for removal of radio-iodines from airstreams and the verification tests which are performed by the user prior to installation of the charcoal into the filter unit. The differences betwen ANSI N509-1976 and ANSI N509-1980, Tables 5-1, reflect a refinement in the test methods used for initial qualification. (See Table 1). PVNGS requests a change to the 1980 standard which has been accepted by the NRC and the acceptance is documented in Section 6.5.1 of the Standard Review Plan, Revision 2, July 1981.

Please be advised that Sections 4.7.7.b.2 and 4.7.7.c, surveillance requirements for the control room essential filtration system, have been changed to reflect ANSI N509-1980, as approved by the NRC in letter dated August 11, 1986 (Amendment No. 7 to Facility Operating License NPF-41 and Amendment No. 1 to Facility Operating License NPF-51).

The purpose of the Combustible Gas Control is to ensure the operability of the equipment and systems required for the detection and control of hydrogen gas will be available to maintain the hydrogen concentrations within containment below its flammable limit during post-LOCA conditions.

The purpose of the ESF Pump Room Air Exhaust Cleanup System is to ensure that radioactive materials leaking from the ECCS equipment within the pump room following a LOCA are filtered prior to reaching the environment. The purpose of the Fuel Building Essential Ventilation System is to ensure the limitations on all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere.

TABLE 1 Summary of Differences Between Tarle 5-1 of ANSI N509-1976 and ANSI N509-1980 A. Physical Characteristics:

1976 1980

1. Particle Size Distribution: ,

Retained on #6 Sieve 0.0% 0.1% max.

Retained on #8 Sieve 5.0% 5.0% max.

Thru #8, Retained on #12 40-60% 60% max.

Thru #12, Retained on #16 40-60% 40% min.

Thru #16, Retained on #16 5.0% max. 5.0% max.

Thru #18, Retained on #16 1.0% max. 1.0% max.

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! l 1976 1980

2. Hardness No. 95 min. 92 min.

3. Ignition Temp (Min) 330*C 330*C

4. CCL4 Activity 60 min. 60 min.

5. Bulk Density (min.) 0.38 gm/ML 0.38g/cm3 B. Perforaance Efficiency

1. Methyl Iodide @ 95% RM 99% at 25'C 97% @ 30*C

2. Methyl Iodide @ 80*C & 95% RH 99% 99%

3. Methyl Iodide @ 130*C, 95% RH 98% 98%

4. Elemental Iodine Retention 99.9% Loading 99.9% min.

99.9% Incl.

Elution

5. Elemental Iodine @ 180*C NA 99.5% min.

B. BASIS FOR NO SIGNIFICANT HAZARDS DETERMINATION The proposed change does not involve a significant hazardu consideration because operation of Palo Verde Units 1 and 2 in accordance with this change would not:

1) Involve a significant increase in the probability or consequences of an accident previously evaluated. 'Ihis change allows for the use of ANSI N509-1980 in lieu of the outdated version, ANSI N509-1976 for acceptance criteria of surveillance tests for Technical Specifications 4.6.4.3.b.2, 4.6.4.3.c , 4.7. 8. b. 2, 4.7. 8.c , 4.9.12.b. 2 and 4.9.12.c. The impact of changing the versions of the standard on the surveillance tests is on the requirements for the charcoal filters when new (unused). The methods of testing and acceptance criteria on used charcoal filters remain the same. The 1980 standard compensates for the fact that the charcoal filters efficiency increases as the temperature increases. The Standard Review Plan, NUREG 0800, section 6.5.1 references ANSI N509-1980. The acceptance criteria of this test still falls within the parameters assumed for the existing safety analysis.

2) Create the possibility of a new or different kind of accident f rom any previously analyzed. No " limiting conditions of operations" are being changed. An updated version of a standard is being incorporated into i the Technical Specifications for use with surveillance requirements as mentioned above, this updated standard has been found to be acceptable to the NRC. Since the 1980 version of the standard has acceptance criteria which are more conservative than the assumptions made for the existing safety analysis, the possibility of a new or different kind of accident will not be created.

- . _ _ _ . . _ . ,__ . . _ - _ ~- - - _ - _ _ _

3) Involve a significant reduction in a margin of safety. As was stated previously, the acceptance criteria of the 1980 version of the standard are more conservative than the assumptions made for the existing safety ,

analysis. The surveillance interval is not being changed, nor is the method of testing. The charcoal filters have been tested to the requirements of ANSI N509-1980 in its entirety and meet those requirements. i l

The Commission has provided guidance concerning the application of the standards for determining whether a significant hazards consideration exists. The proposed change is similar to example (vii), a change to make a license conform to changes in the regulations, where the change results in very minor changes to facility operations clearly in keeping with the regulations. This change modifies the Technical Specifications to include a standard referenced in the Standard Review Plan, NUREG 0800 (1981) instead of one referenced in Regulatory Guide 1.52 Revision 2 (1978).

C. SAFETY ANALYSIS OF THE PROPOSED AMENDMENT REQUEST The essential filtration system is not directly used to help the plant achieve safe shutdown. This system ensures that the off site radiation exposures and exposures to operations personnel in the control room are within the guideline values during and following all credible accident conditions. The PVNGS accident analysis assumes a filter efficiency of 95%. ANSI N509-1976 required new charcoal filter for Methyl Iodide 25'C, 95% RH to be 99% efficient. ANSI N509-1980 requires an efficiency of 97% at 30*C and 95% RH. As called out by Regulatory Guide 1.52 Revision 2, this ANSI Standard is used only for new charcoal filters. The PVNGS filters meet all the criteria for used filters when surveillance tests were performed. Due to the information presented, it is clear that updating the surveillance requirements in the Technical Specifications to include the 1980 version of the ANSI Standard will not increase the probability of occurrence of accidents or malfunctions of equipment important to safety as analyzed in the Final Safety Analysis Report (FSAR).

Because the change does not involve a change to the plant design or the manner in which the plant is operated and the current analyses in the FSAR remain valid, the possibility of any new accident or malfunction is not created.

The NRC has reviewed ANSI N509-1980 and incorporated it as acceptance criteria in the Standard Review Plan, NUREG 0800, Section 6.5.1 Revision 2, 1981. No change is being made to the surveillance interval or the testing method. The essential filtration system will still serve the same purpose and function in the same uanner as before this proposed change.

Therefore, based on the above considerations, ANPP has determined that this change does not involve a significant hazards consideration.

D. ENVIRONMENTAL IMPACT CONSIDERATION DETERMINATION The proposed change request does not involve an unreviewed environmental question because operation of PVNGS Units 1 and 2 in accordance with this change would not:

1. Result in a significant increase in any adverse environmental impact previously evaluated in the Final Environmental Statement (FES) as modified by the staff's testimony to the Atomic Safety and Licensing Board, Supplements to the FES, Environmental Impact appraisals, or in any decisions of the Atomic Safety and Licensing Board; or

2. Result in a significant change in effluents or power levels; or

3. Results in matters not previously reviewed in the licensing basis for PVNGS which amay have a significant environmental impact.

E. PROPOSED TECHNICAL SPECIFICATION CHANGE See attached marked up Technical Specification sections for Units 1 and 2.

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