ML20207P963

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Proposed Tech Specs Re Location of Meteorological Towers & Composition of Independent Safety Engineering Group
ML20207P963
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 01/12/1987
From:
LONG ISLAND LIGHTING CO.
To:
Shared Package
ML20207P885 List:
References
NUDOCS 8701200480
Download: ML20207P963 (6)


Text

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EXHIBIT lA DESIGN FEATURES 5.5 METEOROLOGICAL TOVER LOCATION 5.5.1 The 33 foot meteorological tower shall be located as shown on Figure 5.1.1-1. The 400 foot meteorological tower shall be located as shown on Figure 5.1.3 1.

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

a. A kone, equivalent to less than or equal to 0.95 when flooded with unborated water, which includes a conservative allowance of 1.0% delta k/k for uncertainties as described in Appendix 9A of the PSAR.
b. A nominal 6 inches in one direction and 9.25 inches in the other direction center to center distance between fuel assemblies placed in the storage racks.

5.6.1.2 The k.e, for new fuel for the first core loading stored dry in the spent fuel storage racks shall not exceed 0.98 when aqueous moderation is assumed.

DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent

, inadvertent draining of the pool belov elevation 152'- 4 1/2".

CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity' limited to no more than 2176 fuel assemblies.

.5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The co*ponents identified in Table 5.7.1-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7.1 1.

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' ATTACHMENT 2 TO LICENSE CHANGE APPLICATION 5

1.0 DESCRIPTION

OF CHANGE Change Technical Specification Section 6.3.1 to read,

... except for the Health Physics Engineer who .... " , in-stead of, "... except for the Health Physics Supervisor who

...." The result will be as shown on Exhibit 2.

2.0 REASON FOR CHANGE The use of the term supervisor is inconsistent with the SNPS organization chart specified in Technical Specification Figure 6.2.2-1 " Unit Organization" as well as plant procedures. This change will align the job title in the Technical Specification with the responsibility of the Health Physics Engineer in the SNPS organization chart.

3.0 BASIS FOR NO SIGNIFICANT HAZARDS FINDING In addition to the basic criteria of 10 CFR 50.92(c) addressed below, this amendment request falls within the guidance provided by the Commission (48 FR 14870) regarding examples of amendments that are not likely to involve significant hazards considerations. Specifically, these proposed amendments are " administrative changes to technical specifications: for example, a change to achieve consistency throughout the technical specifications, correction of an error, or a change in nomenclature."

01: Does the change involve a significant increase in the probability or consequences of an accident?

A1: No. The change is merely administrative and is to correct an inconsistency.

02: Does the change create the possibility of a new or different kind of accident from any accident previously evaluated.?

A2: No. The change involves only a nomenclature change.

Q3: Does the change involve a significant reduction in margin of safety?

A3: No. The change is only administrative.

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4.1) ' TIMING OF CHANGE -

Since this is an' administrative change,'LILCO requests.that it-become effective upon issuance of the revised. Technical Specification.

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3 EXHIDIT 2A ADM1[ISTRATIVECONTROLS 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

FUNCTION 6.2.3.1 The ISEG shall function to examine unit operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of unit design and operating experience information, including units of similar design, which may indicate areas for improving unit safety. The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activities or other means of improving unit safety to the Director, Quality Assurance, Safety and Compliance.

COMPOSITION 6.2.3.2 The ISEG shall be composed of at least five, dedicated, multi disciplined, full-time engineers located on site. Each shall have a bachelor's degree in engineering or related science, or equivalent, and at least 2 years professional experience in his field, at least 1 year of which .

experience shall be in the nuclear field.

RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of unit i

activities to provide independent verification

  • that these activities are performed correctly and that human errors are reduced as much as practical.

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! RECORDS 6.2.3.4 Records of activities performed by the ISEG shall be prepared, maintained, and forwarded each calendar month to the Director, Quality 1 Assurance, Safety and Compliance. 1 6.2.4 SHIFT TECHNICAL ADVISOR '

6.2.4.1 The Shift Technical Advisor shall provide advisory technical l support to the Vatch Engineer in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to safe operation of the unit.

The Shift Technical Advisor shall have a bachelor's degree or equivalent in ,

a scientific or engineering discipline and shall have received specific '

training in the response and analysis of the unit for transients and accidents, and in unit design and layout, including the capabilities of instruaentation and controls in the control room.

6.3 UNIT STAFF QUALIFICATIONS l 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1 1971 for comparable positions and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, except for the Health Physics Engineer who shall meet or exceed the qualifications of Regulatory l Guide 1.8, September 1975. The licensed Operators and Senior Operators j shall also meet or exceed the minimum qualifications of the supplemental i requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees.

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  • Not responsible for sign off function.

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