ML20092A871
| ML20092A871 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 01/23/1992 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20092A874 | List: |
| References | |
| NUDOCS 9202100331 | |
| Download: ML20092A871 (5) | |
Text
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,g* H4uy*o, UNITED STATES E'
, w (['g NUCLEAR GEGULATORY COMMISSION g,
^. - t WA2HINJTON, D. C. *20355
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s-CCNSUMERS POWER _COMPAlq DOCKET NO. 5C-255 PAtISADES PUE AMENDMENT 10 FACILITY OPERATING LICENSE Amendment No. 140 License No. DPR-20 1.
The Nuclear Regulctory Commission (tne Commission) has found that:
A.
The application fe" amendment by Consumers Power Company (the licensee) dated October 28, 1991., complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comniissica's rules and regulations set fortii in 10 CFR Chapter I; B.
The fucility will operate in conformity witn the application, the provisions of the Act, and the rules and regulations of the Ccmmission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can te conducted without endangerirg the health and safety of the public; and (ii) that such activitiec 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; 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 the license amendment and Paragraph 2.C.2 of Facility Operating License No. DPR-20 is hereby amended to read as follows:
9202100331 920123 hDR ADOCK 0500 2
.+
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Technical Specifications a
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.140, 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 its date'of issuance.
FOR THE NUCLEAR REGULATORY C014 MISE 20N b.
L. B. Marsh, Director Project Directorate 111-1 Division ci ?eactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of. Issuance: January 23, 1992 i
w 7 FMENTEJCENSE iMENDMENT NO.140
.~j FACILI'Y SPER!,.2 L t_IC_Eji NO. DPR-20 LOCK 0T NO. 50-?$5 e
Revise /\\ppendix A 7erhnkal Fpe.ifications t>; vetoving the pages identified below and inreet!?g r.he attached paqor The rw sed pages are identified by g'.,-
tM wendme-t nutoer and contain rcUir ni lincc sndicating the area of change.
,Rjh31 INSERT 5-4 5-4
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~4 5-4a 5-4a 5
Y
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- e a
34
5.4 LUD. STORAGE 5.4.1 Few Fuel Storace a.
The pitch of the new fuel storage rack lattice is 29.375 inches, and every othe' position in the lattice shall be permanently occupied by an 8" x 8" structural steel box beam or core plugs such that the minimum center-to-center spacing of new fuel assemblies in the alternating storage array is 13.26".
This distance in the alternating storage lattice is sufficient so th:t K will not exceed 0.95 where fuel assemblies with 216 U0 or Gd 0 -dM fuel rods 2
23 2
or metal rods and a maximum average planar enrichment in the U0, or Gd 0 U0 fuel rods of 4.20 w/o U 'ed K are in place and optimum moberatfon is assumed.
3 The calculft includes appropriate conservatisms as described in Siemens NucTear Power Corporation Report EMF-91-1421(NP).
b.
New fuel may also be stored in shipping containers.
c.
The new fuel storage racks are designed as a Class I structure.
i I
5-4 Amendment No JE, f9, JpE,140
5.4.2 Soent Fuel Storace i
Irradiated fuel bundles will be stored, prior to off-site shipment a.
in the etainless steel-lined spent fuel pool.
b.
(Deleted)
The spent fuel storage pool and spare (north) tilt pit are divided c.
into two regions identified as Region I and Region II as illustrated in Figure 5.4-I.
Region i racks are designed and shall be maintained with a nominal 10.25" center-to-center distance between fuel assemblies with the exception of the single Type E rack which has a nominal 11.25" center-to-center distance between fuel assemblies. The Region I spent fuel storage racks are designed such that fuel having a maximum assembly planar average U enrichment of 4.40 w/o placed in the racks would result in a K,233 equivalent to g
5 0.95 when flooded with unborated water.
The K ' of $ 0.95 includes a
conservative allowance for uncertaiI[ ties.
For enrichments above 3.27 w/o V
, the fuel assemblies must contain 216 rods which are either UO '
0 -U0 or solid metal.
2 23 2
d.
Region 11 racks have a 9.17 inch center-to-center spacing. Because of this smaller spacing, strict controls are employed to evaluate burnup of the fuel assembly prior to its placement in Region II cell locations.
Upon determination that the fuel assembly meets the burnup requirements of Table 5.4-1, placement in a Region 11 cell is authorized.
These positive controls assure the fuel enrichment limits assumed in the safety analyses will not be exceeded.
e.
(Deleted) f.
The minimum spent fuel poc1 water boron concentration shall be l20 ppm.
Baron concentration shall be verified at least once monthly.
g.
The spent fuel racks are designed as a Class I structure, h.
(Deleted) i.
Storage in Region II of the spent fuel pool and spare (north) tilt pit shall be restricted by burnup and enrichment limits specified in Table 5.4-1.
NOTE: Until needed for fuel storage, one Region 11 rack in the northeast corner of the spent fuel pool may be removed and replaced with the cask anti-tipping device.
References FSAR Update Chapter 5 l
FSAR Update Chapter 9 5-4a Amendment No. JEE, JJJ,140 i
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