ML20217N931

Proposed Tech Specs 5.5 Re Meteorological Tower Location

ML20217N931
Person / Time
Site:	McGuire, Mcguire
Issue date:	03/03/1998
From:	DUKE POWER CO.
To:
Shared Package
ML20217N924	List: ML20217N918 ML20217N931
References
NUDOCS 9803090339
Download: ML20217N931 (17)

Text

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/%A ENro ONLY DESIGN FEATURES FUEL ASSEMBLIES Continued) to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core regions.

CONTROL. RQD ASSEMBLIES 5.3.2 The core shall contain 53 full-length and no part-length control rod assemblies. The full-length control rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material for Unit I control rbds shall be 80% silver,155 indium, and 5% cadmium. All control rods shall be clad with stainless steel tubing.

5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:

a. In accordance with the Code requirements specified in Section 5.2 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements,

b. For a pressure of 2485 psig, and

c. For a temperature of 650*F, except for the pressurizer which is 680*F.

VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is 13,050 l i 100 cubic feet at a nominal T, of 525'F.

5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.

5.6 FUEL STORAGE CRITICALITY 5.6.1 a. The spent fuel storage racks are designed and shall be maintained with:

1) y s 0.95 if fully flooded with unborated water as des,cribed in Section 9.1 of the FSAR; and

2) A nominal 10.4' center to center distance between fuel assemblies placed in Region 1; and

3) A nominal 9.125" center to center distance between fuel assemblies placed in Region 2.

McGUIRE - UNIT 1 5-7 Amendment No.175 0 9003090339 980303 .

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ATTACHMENT III DESCRIPTION OF PROPOSED CHANGES AND TECHNICAL JUSTIFICATION i

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US NRC Attachment III

. March 3, 1998 Page 1 of 2 DESCRIPTION OF PROPOSED CHANGES:

The location of the existing meteorological tower will be used for site construction. The existing tower will be decommissioned and a new tower will be built in a new location. Figure 5.1-1 of I Technical Specification 5.5 is changed to show the location of i the new meteorological tower. Additionally, Figure 5.1-1 is )

replaced by a new figure (Attachment II) which is more legible I and shows additional site physical changes. Technical Specification 5.1.1 requires the Exclusive Area to be shown on Figure 5.1-1. Technical Specification 5.1.1 is not affected by the proposed change regarding meteorological tower location and new Figure 5.1-1.

TECHNICAL JUSTIFICATION:

Duke Power committed to Regulatory Guide (RG) 1.23 (Safety Guide i

23)

• Onsite Meteorological Programs", Revision 0, 1972.

Regulatory Position C.2 of this RG specifies:

"The tower or mast should be sited at approximately the same elevation as finished plant grade and in an area where plant i structures will have little or no influence on the meteorological measurements. The lower set of instruments should sense wind speed and direction, temperature, and dew point (where required) at an elevation of 10 meters above the j ground and the upper set should sense wind speed and direction and temperature at the height of release of radioactive material (plant vent height) but should be pon tioned not less than 30 meters above the lower sensor set. Fu. stack releases, another set of sensors should be located at an elevation such that meteorological conditions at stack height can be represented."

For the new meteorological tower location, Duke continues to commit to Regulatory Position C.2 of RG 1.23, Revision 0 and used the detailed guidance in Section 4 of approved ANSI /ANS-2.5-1984, American National Standard for Determining Meteorological Information at Nuclear Power Sites, for siting the new tower. It should be noted that Section 4 of this ANSI standard, Siting of Meteorological Instruments, is consistent with Regulatory Position C.2 of Proposed Revision 1 to Regulatory Guide 1.23, September 1980. It should also be noted that in Second Proposed Revision 1 to Regulatory Guide 1.23, April 1986, the Nuclear Regulatory Commission endorsed ANSI /ANS-2.5-1984.

The proposed new location meets the recommendations of Section 4 of ANSI /ANS-2.5-1984. The proposed new location is in an open area on the bank of Lake Norman, approximately 1350 feet north of the reactor buildings. Ground elevation at the new location is

US NRC Attachment III

- Mar'ch 3, 1998 Page 2 of 2 767.1 feet mean sea level which is approximately the same elevation as McGuire finished plant grade. The measuring heights for meteorological instruments on the new tower are 10 meters and -

60 meters relative to ground elevation. The distance requirement of 10 times an obstruction height as recommended by ANSI /ANS-2.5-1984, Section 4 will be met. For example, at a distance of 100 meters from the new tower location, there will be no trees or plant structures with heights higher than 10 meters; at a distance of 600 meters from the new tower location, there will be no trees or plant structures with heights higher than 60 meters.

Tower construction will be in accordance with national standard ANSI /EIA-222-E-1991.

Based on a five year period from 1992-1996, the prevailing onsite wind directions are (SSW, S, NE) at the 10 m level and (SSW, NNE) at the 40 m level of the existing tower. Depending upon the prevailing winds at a given time, the new tower eay be downwind i of plant structures and the thermal discharge canal. However, the new tower meets the distance to height recommendation of ANSI /ANS-2.5-1984, Section 4. Therefore, the effects of structures on air flow will not adversely affect measurements.

There will be negligible heat dissipation effects on meteorological measurements based on the height at which j measurements are taken relative to the distance of the new tower i from the discharge canal. l It should be noted that this technical specification has been 1 proposed to be relocated to the UFSAR in McGuire's 5/27/97  ;

proposed Improved Standardized Technical Specifications, j consistent with the recommendations of NUREG-1431. l UFSAR Sections 2.3 and 16.7-3 and Figures 2-4, 2-41 and 2-42 will require changes as a result of this proposed Technical Specification change. These UFSAR items will be revised appropriately following approval of this amendment by the Nuclear Regulatory Commission. j l

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6 ATTACHMENT IV NO SIGNIFICANT HAZARDS CONSIDERATIONS 1

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US NRC Attachment IV

, March 3, 1998 Page 1 of 2 No Sicrnificant Hazards Considerations:

In accordance with the criteria set forth in 10 CFR 50.91 and 50.92, the McGuire Nuclear Station'has evaluated this proposed j Technical Specification change and determined it does not represent a significant hazards consideration. The following is provided in support of this conclusion.

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1. Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?

No. The proposed change involves the location of the metectological tower. The meteorological tower is mainly used i

for post-accident radiological release assessment and does not impact the initiation or mitigation of previously analyzed accidents. No change in routine or accident radioactive release diffusion estimate methods is made. The new location is approximately twice as far as the old location from the reactor buildings. Within a radius of 60 meters of the new location, there is no significant structure that the tower can reach if it falls down. A fall of the tower due to natural or man-made causes will not adversely affect Category I structures such as the reactor buildings, auxiliary building, spent fuel pool buildings, diesel generator buildings, and control room. These  ;

structures have been analyzed for effect from tornado missiles )

comparable to or more severe than those possibly generated from a '

failed tower. The results of these analyses showed that no safety limit was exceeded due to tornado missiles.

l The new location and tower do not involve a significant increase l in the probability or consequences of an accident previously l evaluated.  ;

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2. Does the change create the possibility of a new or different i kind of accident from any accident previously evaluated?  !

No. The proposed change involves the location of the j meteorological tower. The new tower, like the old one, is j separated from other systems in the plant. No physical changes l to other systems or changes in methods governing normal plant operation are made as a result of this proposed change. Failure of the new tower due to either man-made or natural causes should not create any new effects than those described above.

The new location and tower do not create the possibility of a new or different kind of accident from any accident previously evaluated.

US NRC Attachment IV

, March 3, 1998 Page 2 of 2

3. Does this change involve a significant reduction in a margin

-of safety?

No. The proposed change involves the location of the meteorological tower. The proposed change does not involve any physical change to other systems in the plant and has no impact on any safety analysis assumptions. Therefore, this change does not involve a reduction in a margin of safety.

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- l ATTACHMENT V ENVIRONMENTAL IMPACT ASSESSMENT l

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US NRC Attachment'V

, March'3, 1998 Page 1 of 1 Envirosumental Impact Assessment:

The proposed Technical Specification amendment has been reviewed against the criteria of 10 CFR 51.22 for environmental considerations. The proposed amendment does not involve a significant hazards' consideration, nor increase the types and amounts'of effluents that'may be released offsite, nor increase individual or. cumulative occupational radiation exposures.

Therefore, the proposed amendment meets the criteria given in 10 CFR 51.22 (c) (9) for'a categorical exclusion from the requirement for an Environmental Impact Assessment.

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