ML14183A088
| ML14183A088 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 01/20/1987 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14183A089 | List: |
| References | |
| DPR-23-A-112 NUDOCS 8702030374 | |
| Download: ML14183A088 (7) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 CAROLINA POWER AND LIGHT COMPANY DOCKET NO. 50-261 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 112 License No. nPR-23
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Carolina Power and Light Company (the licensee) dated October 13, 1986, as supplemented by letter dated December 11, 1986 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter 1; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-23 is hereby amended to read as follows:
8702030374 870120 PDR ADOCK 05000261 P
-2 (P) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.112, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Lester ubenstein, Director PWR Project Directorate #2 Division of PWR Licensing-A Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 2Q, 1987
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 112 FACTLITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 Revise Appendix A as follows:
Remove Pages Insert Pages 4.1-10 4.1-10 5.3-1 5.3-1 5.4-1 5.4-1 5.4-2
(HBR-39)
TABLE 4.1.2 FREQUENCIES FOR SAMPLING TESTS Maximum Time Between Check Frequency, Tests
- 1. Reactor Coolant Samples Cross.Activity (1) Minimum I Per 72 hrs.
3 days
- Radiochemical (2)
Monthly 45 days
- Radiochemical for 1 per 6 mos. (6)(7) 6 months E Determination Isotopic Analysis 1 per 14 days (7) 14 days for Dose Equivalent 1-131 Concentration Isotopic Analysis a) Once per 4 for Iodine Includ-hours (8) ing 1-131, 1-133 b) One sample (9) and 1-135 Tritium Activity Weekly 10 days Cl & 02 5 day/week 3 days
- 2. Reactor Coolant Boron concentration Twice/week 5 days Boron
- 3. Refueling Water Boron concentration Weekly 10 days Storage Tank Water Sample
- 4. Boric Acid Tank Boron concentration Twice/week 5 days
- 5. Spray Additive NaO8 concentration Monthly 45 days Tank
- 6. Accumulator Boron concentration Monthly 45 days
- 7. Spent Fuel Pit Boron concentration Prior to Refueling or NA*
New Fuel Movement in the Spent Fuel Pit
- 8. Secondary Coolant Gross activity Minimum 1 Per 72 hrs.
3 days Isotopic Analysis a) 1 per 31 days (10) for Dose Equivalent b) 1 per 6 months (11) 1-131 Concentration
- 9. Stack Gas Iodine 1-131 and particulate Weekly (3) 10 days
& Particulate radioactivity Samples releases
- 10. Steam Generator Primary to secondary 5 days/week 3 days Samples tube leakage 4.1-10 Amendment No.
7,112
(HBR-39) 5.3 REACTOR 5.3.1 REACTOR CORE 5.3.1.1 The reactor core contains approximately 68 metric tons of uranium in the form of natural or slightly enriched uranium dioxide pellets.
The pellets are encapsulated in Zircaloy-4 tubing to form fuel rods which are all pre-pressurized.
The reactor core is made up of 157 fuel assemblies. Each fuel assembly contains 204 fuel rod locations occupied by rods consisting of natural or slightly enriched uranium pellets, solid inert materials, or a combination of the aforementioned.(1) 5.3.1.2 Deleted 5.3.1.3 Reload fuel will.be similar in physical design to the initial core.
The enrichment of reload fuel will be no more than 3.9 weight percent of U-235.
5.3.1.4 Deleted 5.3.1.5 There are 45 full-length RCC assemblies in the reactor core.
The full-length RCC assemblies contain 144-inch segments of silver indium-cadmium alloy clad with stainless steel.(2) 5.3.1.6 Doleted 5.3.2 REACTOR COOLANT SYSTEM 5.3.2.1 The design of the Reactor Coolant System complies with th6 code requirements.(3) 5.3-1 Amendmcnt No. 1t0f 112
(HBR-39) 5.4 FUEL STORAGE 5.4.1 SPENT FUEL PIT The new and spent fuel pit structures are designed to wi hstand the anticipated earthquake loadings as Class I structures. The spent fuel pit has a stainless steel liner to ensure against loss of water.(1) 5.4.2 CRITICALITY 5.4.2.1 NEW FUEL STORAGE RACKS Due to the new fuel storage rack design, a nominal 21-inch center-to-center distance is maintained between fuel assemblies. To permit storage of fuel with a maximum assembly axial plane enrichment of 3.9 weight percent U-235, additional separation is maintained by use of any of the storage rack location options below(2) in order to establish a geometry which ensures that keff is less than 0.95 assuming the new fuel storage racks are flooded with unborated water and which assures that keff is less than 0.98 in an optimum moderation event.
The four listed options provide fuel storage locations which are secured to prevent fuel storage in those locations OPTION A:
B4,6,8,10 / C3,5,7,9 / D4,6,8,10 / E3,5,7,9 I F4,6,8,10 / G3,5,7,9 84,6,8,l0 / J3,5,7,9 OPTION B:
C4,5,6,7,8,9 / D4,5,6,7,8,9, / E4,5,6,7,8,9, I F4,5,6,7,8,9 C4,5,6,7,8,9 / 84,5,6,7,8,9 OPTION C:
C4,5,6,7,8,9 / D4,5,6,7,8,9 / E4,5,8,9 I F4,5,8,9 I C4,5,6,7,8,9 H4,5,6,7,8,9 OPTION D:
C4,5,6,7,8,9 / D4,5,8,9 / E4,5,8,9 / F1,4,5,8,9 / G1,4,5,8,9 1,4,5,6,7,8,9 I Jl Kl 5.4-1 Amendment No. $t,1
(HBR-39) 5.4.2.2 SPENT FUEL STORAGE PIT A combination of nominal assembly spacing and neutron absorbent material between stored assemblies is maintained to ensure that keff is less than 0.95 when flooded with unborated water based on a maximum assembly axial plane enrichment of 3.9 weight percent U-235.
5.4.3 BORON CONCENTRATION -
SPENT FUEL STORA'E PIT The spent fuel storage pit is filled with borated water at a concentration of greater than or equal to 1500 ppm during refueling operations or new fuel movement in the spent fuel storage pit. This minimum boron concentration ensures subcriticality under worst case design events.
5.4.4 STORAGE CAPACITY -
SPENT FUEL STORAGE PIT The spent fuel storage pit provides a storage location for 544 fuel assemblies.
Reference (1) FSAR Section 9.1 (2) IN-NF-86-100, "Final Report, Criticality Safety Analysis, H. B. Robinson New Fuel Storage Vault with 4.2 Percent Enriched 15 x 15 Fuel Assemblies, August, 1986" A
- 7.
Amendment No.
112