ML17303A691

Application for Amends to Licenses NPF-41,NPF-51 & NPF-65, Changing Tech Specs to Correct Table 3.3-6 Re Measurement Ranges of Main Steam Effluent Line Monitors.Fee Paid

ML17303A691
Person / Time
Site:	Palo Verde
Issue date:	11/20/1987
From:	Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML17303A692	List: ML17303A691 ML17303A693
References
161-000666-EEVB, 161-666-EEVB, TAC-66779, TAC-66780, TAC-66781, NUDOCS 8711240255
Download: ML17303A691 (10)

Text

REGULA i uRY INFORMATION DISTR IBUTI(.. SYSTEM (BIDS)

ACCESSION NHR: S711240255 DQC. DATE: S7/1 1/20 NOTARIZED: NO DOCKET 0 FACIL: hTN-50-52S Palo Verde Nuclear Stationi Unit ii Arizona Publi 05000528 BTN-50-529 Palo Verde Nuclear Stations Unit 2i Arizona Publi 05000529 STN-50-530 Palo Verde Nuclear Stations Unit 3i Arizona Publi 05000530 AUTH. NAME AUTHOR AFF ILI AT ION VAN BRUNT'. E. TU Electric (formerly Texas Utilities Generating Co. )

RECIP. NAME REC1P IENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Application for amends to Licenses NPF-41i NPF-51 h Tech Specs to correct Table 3. 3-6 re measurementNPF-65'hanging ranges of main steam effluent line monitors. Fee paid.

DISTRIBUTION CODE: A001D COPIES RECEIVED: LTR l ENCL l SIZE: ~+

TITLE: OR Submittal: General Distribution NOTES: Standardized plant. 0500052a Standardized plant. 05000529 Btandardi zed p lant. 05000530 REC IP IENT COP IEB RECIPIENT COP IEB ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 0 PD5 PD 5 5 LICITRAiE 1 1 DAVIS' 1 1 INTERNAL: ACRS 6 6 ARM/DAF/LFMB 1 0 NRR/DEBT/ADS 1 1 NRR/DEBT/CEB 1 1 NRR/DEBT/MTB 1 1 NRR/DEBT/RBB 1 1 NRR/DOEA/TSB 1 NRR/PMAS/ILRH 1 OGC/HDSi 1 0 01 1 1 RES/DE/EIB 1 1 EXTERNAL'GGG BRUBKEz B 1 1 LPDR 1 1 NRC PDR 1 NBIC 1 1 NOTES:

TOTAL NUMBER OF CQP I ES REGU IRED: LTTR, 29 ENCL 26

Arizona Nuclear Power Project P.O, BOX 52034 ~ PHOENIX. ARIZONA85072-2034 161-000666-EEVB/LJM November 20, 1987 Docket Nos STN 50-528/529/530 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 ATTN: Document Control Desk

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2 and 3 Technical Specification Amendment - Section Table 3.3-6 File: 87-F-005-419.05; 87-B-056-026; 87-C-056-026; 87-D-056-026 Attached please find the proposed changes to the PVNGS Units 1, 2 and 3 Technical Specifications. The changes correct the measurement ranges of the Main Steam Effluent Line Monitors of Table 3.3-6. We request 30 days to implement the change after the date the change becomes effective.

Enclosed, with this amendment request package are the following:

A. Description of the Technical Specification Amendment Request.

B. Purpose of the Technical Specification.

C. Need for the Technical Specification Amendment.

D. Basis for Proposed No Significant Hazards Consideration Determination.

E. Safety Analysis for the Amendment Request.

F. Environmental Impact Consideration Determination.

G. Marked-up Technical Specification Change Pages.

By copy of this letter, we are also forwarding the proposed changes to the appropriate state agency.

In accordance with the requirements of 10CFR170.12(c), the license amendment application fee of $ 150.00 has been forwarded to the USNRC License Fee Management Coordinator.

PDR

~+o>>S amaggo p ADOCK 05000528 PDR (00)

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Mr. George W. Knighton November 20, 1987 Page 2 161-00666-EEVB/ZJM If you have any questions, please call A. C. Rogers at (602) 371-4087.

Very tru you E. E. Van Brunt, Jr.

Executive Vice President Project Director EEVB/LJM/ls Attachments cc: 0. M. De Michele J. R. Ball J. B. Martin E. A. Licitra A. C. Gehr C. E. Tedford R. M. Diggs (with WFD $ 150.00)

ATTACHMENT A. DESCRIPTION OF THE TECHNICAL SPECIFICATION AMENDMENT RE UEST The proposed amendment corrects the measurement ranges of the Main Steam Line Effluent Monitors, as set forth in Technical Specification (T.S.) Table 3.3-6.

B. PURPOSE OF THE TECHNICAL SPECIFICATION The purpose of Table 3.3-6 is to identify the radiation monitoring instrumentation channels and to define their operability during the identified plant modes. The table also specifies the alarm/trip set points and the specific ACTION for each of the identified monitors.

EED FOR THE TECHNICAL SPECIFICATION AMENDMENT, .

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The measurement range of tge Main7Steam Line Effluent Monitors stated in Table 3.3-6 (RU-139 and 140) (10 to 10 mR/hr) is the range of the detector section of the monitors i.e.,the range of measurable detectable radiation. The range of the measuring section of thei monitors iOe.', the> range of accurately measured detectable radiation, is smaller (10 to 10 mR/hr). Because no clarification is made in the T.S., the operator must be. aware of this fact to understand and use the table 'orrectly. ,The, proposed change would eliminate the need for prior knowledge and would ensure a clearer understanding of the table. Stating the smaller range of the monitors in the T.S. has no affect on the qualification of the monitors to Regulatory Guide 1.97.

D. BASIS FOR PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION

1. The Commission has provided standards for determining whether a significant hazards consideration exists as stated in 10CFR50.92. A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation of the facility in accordance with a proposed amendment would not: (1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) Involve a significant reduction in a margin of safety.

A discussion of these standards as they relate to the amendment request follows:

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

The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated because the proposed change corrects the measurement ranges of the Main Steam Line Effluent Monitors. The corrected numbers have been reverified and meet the requirements of Regulatory Guide 1.97. Since the requirements of 1.97 are met, no change to the safety analysis has been made and therefore, there will be no significant increase in the probability or consequences of an accident previously evaluated.

lt

~s Standard 2--Create the possibility of a new or different kind of accident from any accident previously evaluated.

The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated because the proposed change does not change the assumptions made for the safety analysis as it pertains to the monitors. The requirements of regulatory Guide 1.97 are still met and therefore, the assumptions are still the same.

Standard 3--Involve a significant reduction in a margin of safety.

The proposed change does not involve a significant reduction in a margin of safety because the proposed change does not change the assumptions made for the safety analysis as it pertains to the monitors.

2. The proposed amendment matches the guidance concerning the application of standards for determining whether or not a significant hazards consideration exists (51FR7751) by example:

(i) A purely administrative change to Technical Specifications: for example, a change to achieve consistency throughout the Technical Specifications, correction of an error, or a change in nomenclature.

SAFETY EVALUATION FOR THE AMENDMENT RE UEST The proposed Technical 'Specification amendment 'ill not increase probability of occurrence or the consequen'ces of an accident or malfunction of the equipment important to safety previously evaluated in the FSAR. The proposed change further defines the actual measurement ranges of the Main Steam Line Effluent Monitors. The proposed change does not change any of the assumptions of the safety analysis as it pertains to the monitors.

Technical Specification " Amendment will 'not increase ll The proposed

(

the probability for an accident or malfunction of a different type than any previously evaluated in the FSAR. The proposed change has not physically changed the monitors or limited the operations of said monitors in any way therefore, ensuring that the possibility of a different accident or malfunction will not be created.

The proposed Technical Specification amendment will not reduce the margin of safety as defined in the basis for the Technical Specification. The proposed change does not change any of the assumptions of the safety analysis as they pertain to the monitors and therefore does not change the basis.

The following is the calculation assuring qualification of the monitors to Regulatory Guide 1.97. The range as specified in RG 1.97 is 1E-1 to 1E 3 uci/cc. Utilizing conversiog factors from EPIP 14A section 4.3.2.3 and the ANPP monitors'anges of 10 to 10 R/hr.

the monitor's, lower range is equal to

-3 -

10 R/hc (.078) ~uci cc 7.8E -2 uci/cc

'R/hr which is less than the low range specified by 1.97 of 1E-1 uci/cc and the monitor's upper range is equal to 2

10 R/hc (15.6) ~uci cc - 1.56E + 6 uci/cc mR/hr or 2

10 R/hc (.078) ~uci cc - 7.8E + 3 uci/cc mR/hr either of which is greater than the high range specified by 1.97 of 1E 3 uci/cc. Therefore, the ANPP monitors satisfy the requirements of 1.97.

F. ENVIRONMENTAL IMPACT CONSIDERATION DETERMINATION The proposed change request does not involve an unreviewed environmental question because operation of PVNGS Unit 1, 2 and 3, 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; 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.

G, MARKED-UP TECHNICAL SPECIFICATION CHANGE PAGES Limiting Conditions For Operation And Surveillance Requirement; 3/4 3-38

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