ML20042G148
| ML20042G148 | |
| Person / Time | |
|---|---|
| Site: | Summer  (NPF-12-A-088, NPF-12-A-88) |
| Issue date: | 05/08/1990 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20042G149 | List: |
| References | |
| NUDOCS 9005110149 | |
| Download: ML20042G148 (4) | |
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'1 CORRECTION T0 LICENSE AMEN 0 MENT NO. 88 TO FAClllTY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 Replace the following pages of the Appendix A Technical Specifications with 1
the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
u Remove Pages Insert Pages 6-16 6-16 6-16a 6-18 6-18 6-18a 1
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9005110149 900508 i
PDR ADOCK 0500039'"
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ADMINISTRATIVE CONTROLS e.
-Type of container (e.g., LSA Type A, Type B, Large Quantity), and f.
Solidification agent (e.g., cement, urea formaldehyde).
The radioactive effluent release reports shall include unplanned releases from site to unrestricted areas of. radioactive materials-in gaseous and liquid effluents on a quarterly basis.
~The radioactive effluent release reports shall include any changes to the Process Control Program (PCP) made during the reporting period.
MONTHLY OPERATING REPORT 6'9.1.10 Routine reports of operating statistics and shutdown experience, in-ciuding documentation of all challenges to the PORV's or safety valves, shall be-submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, with a copy to the Regional Office of Inspection and Enforcement, no later than the 15th of each L
month following the. calendar month covered by the report.
Any changes to the 0FFSITE DOSE CALCULATION MANUAL shall be submitted with the a
Monthly Operating Report within 90 days in which the change (s) was made effective.
In addition, a report of any major changes to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted as set forth in 6.5 above.
CORE OPERATING LIMITS REPORT 6.9.1.11 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT prior to each reload cycle, or prior to any.
remaining portion of a reload cycle, for the following:
a.
Moderator Temperature Coefficient BOL and E0L Limits and 300 ppm surveillance limit-for Specification 3/4.1.1.3, b.
Shutdown Bank Insertion Limit for Specification 3/4.1.3.5, c.
Control Bank Insertion Limits for Specification 3/4.1.3.6, ND d.
-Axial Flux Difference Limits, target band, and APL for l
Specification 3/4.2.1, RTP e.
Heat Flux Hot Channel Factor, F
, K(Z), W(2), AP h and W(Z)BL q
for Specification 3/4.2.2, f.
Nuclear Enthalpy Rise Hot Channel Factor, F and Power Factor l
Multiplier, PFAH, limits for Specification 3/4.2.3.
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The analytical methods used to determine the core operating limits shall be l
those previously reviewed and approved by the NRC, specifically those described in the following documents:
l a.
WCAP-9272-P-A, " WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY",
l July 1985 (W Proprietary).
SUMMER - UNIT 1 6-16 Amendment No. 79, 88 1
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ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient, 3.1.3.5 - Shutdown Bank Insertion Limit. 3.1.3.6 -
Control Bank Insertion Limit, 3.2.1 - Axial Flux Dif ference, 3.2.2 -
Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).
b.
WCAP-10216-P-A, " RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FQ SURVEILLANCE TECHNICAL SPECIFICATION", June 1983 (W Proprietary).
(Methodology for Specifications 3.2.1 - Axial Flux Difference (Relaxed Axial Offset Control) and 3.2.2 - Heat Flux Hot Channel Factor (FQ Methodology for W(Z) surveillance requirements).)
c.
WCAP-10266-P-A, Rev. 2, "THE 1981 VERSION OF WESTINGHOUSE EVALUATION MODEL USING BASH CODE",' March 1987 (W Proprietary).
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor).
The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements there.to shall be provided upon issuance, for each reload cycle, to the'NRC Document Control Desk with copies to the Regional Administrator and l
Resident Inspector.
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' SUMMER - UNIT 1 6-16a Amendment No. 88
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ADMINISTRATIVE CONTROLS i
e.
Records of transient or operational cycles for those unit components identified in Table 5.7-1.
f.
Records of reactor tests and experiments.
g.
Records of training and qualification for current members of the unit staff.
h.
Records of in-service inspections performed pursuant to these Technical Specifications.
i.
Records of Quality Assurance activities as specified in the NRC's approved SCE&G position on Regulatory Guide 1.88, Rev. 2, October 1976.
j.
Records of reviews performed for changes made to procedures or equipment or reviews of-tests and experiments pursuant to 10 CFR 50.59.
k.
Records of meetings of the PSRC and the NSRC.
1.
Records of the service lives of all hydraulic and mechanical snubbers defined in Section 3.7.7 including the date at which the service life commences and associated installation and maintenance records.
m.
Records of secondary water sampling and water quality, n.
Records of analysis required by the radiological environmental monitoring program.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the
> intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP)
- Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area.
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" Health Physics personnel or personnel escorted by Health Physics personnel l:
shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they otherwise comply with approved radiation protection procedures for entry into high radiation areas.
SUMMER - UNIT 1 6-18 Amendment No. 35, H, 75, l
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