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MEMORANDUM FOR: 6 Assistant Director
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Division of Licensing i
FROM:
R. W. Houston, Assistant Director for Reactor Safety Division of Systems Integration
SUBJECT:
CSB RELATED INPUT RE: PRIORITIZATION OF MISSISSIPPI POWER & LIGHT'S (MP&L) TECHNICAL SPECIFICATION PROBLEM SHEETS FOR GRAND GULF, UNIT 1 (TACS 54458)
The Containment Systems Branch (CSB) has completed the review requested under TACS No. 54458. This review involved certain Technical Specifications (TS) problem sheets for the Grand Gulf Nuclear Station, Unit 1, as prepared by MP&L.
The work request was to assign priorities to the CSB related TS problem sheets.
The CSB has identified 25 TS problem sheets which are within its scope of responsibility. We consider four of the 25 items to be high priority items, i.e., resolution of these items should be completed before authorizing operations above 5% of full power. The high priority items are 20, 68, 69 and 235.
Three of these four were previously identified and recommended by the CSB (Enclosure 1). Our previous recommendations have not yet been incorporated into the present version of the GGNS TS.
Comments 2, 3 and 4 of Enclosure 1, correspond to MP&L TS problem items 68, 20 and 69, respectively.
We consider the remaining 21 items to be low priority items, i.e., operations above 5% of full power can be authorized without prior resolution of these
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i tems. However, we recommend that these items be resolved before completion of the first refueling outage. The twenty-one items are 4, 12, 19, 31, 67, 107, 126, 127, 128, 140, 144, 167, 169, 170, 171, 172, 209, 230, 231, 232, and 240.
These low priority items are predominantely' administrative in nature; and some of the proposed changes are functionally less restrictive than what is now in place. Should you have problems or questions with our assessment, please contact us.
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R. W. Houston, Assistant Director for Reactor Safety Division of Systems Integration
Enclosure:
As stated cc:
R. Mattson R. Capra D. Hoffman D. Houston L. Kintner g
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MEMORANDUM FOR:
T. Novak, Assistant Director for Licensing, DL F. Miraglia, Assistant Director for Safety Assessment, DL FROM:
R. W. Houston, Assistant Director for Reactor Safety, DSI
SUBJECT:
CSB RELATED INpVT RE:
REVIEW 0F THE GRAND GULF, UNIT 1 TECHNICALSpECIFICATIONS(TAC #52412)
REFERENCE:
Letter from L. F. Dale to H. Denton, dated September 12, 1983,.. Correspondence No. AECM-83/0540.-
The CSB has completed it's review of the Technical Specifications (TS) for Grand Gulf; Un.it I which. pertain to its area of responsibility. Specifi-cally, the CSB review was focused on TS Section 3/4.6.
It should be noted that other' ranches have overlapping responsibilities for portions of TS Section 3/4.6, particularly the ASB, RSB, and ICSB. Therefore, we expect those branches to verify and comment on their pertinent areas.
The following are the CSB's comments and/or recomended modifications to the Grand Gulf, Unit 1, Technical Specifications:
- 1) Surveillance Reg'uirement Section 4.6.1.2 should be modified as out-lined in Attachment 1; Y
2)
Limiting Condition for,0peration 3.6.1.9 should be modified to indi-cate that the 20-inch and 6-inch purge systems shall not be used at the same time; 3)
Regarding Table 3.6.4.1, the superscript footnotes (c) and (d) on selected isolation valves should be deleted according to the isola-tion valves identified with the appropriate schedule as obtained -
from the referenced letter; I
4)
Regarding Surveillance Requirement Section 4.6.7.2.a a footnote reference should be added at the end of the word " energized" to indicate that a minimum of one igniter on each redundant circuit within a region or enclosure must be demonstrated operable via test.
K. W. Houston, Assistant Director for Reactor Safety
Enclosure:
As Stated cc:
A. Schwencer C. O. Thomas F. Eltawila
Contact:
LMMnneasco, CSB:DSI, 29485 so s q<l L M e.? E I pl T K ~
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s,,,4 MAR 1 ISS3 MEMORANDUM FOR:
C. Thomas, Chief Standardization and Special Projects Branch, DST FROM:
W. Bu~tl er, Chief Containment Systems Branch, DSI SUBJECT :
RECOMMENDED CHANGE TO THE STANDARD TECHNICAL SPECIFICATIONS
_ Surveillance requirement 4.6.1.2. Item. C.1 of the Standard Technical
~ ; Specifications, which is identical 'to Item III.A.3.b of Appendix J to 10 CFR Part 50 is not well wrded since if.the test is properly perfomed, the difference between the supplemental and the Type A tests can never be 4 0.25 La. Therefore, it-is recommended that Item 4.6.1.2.c.1 of the Standard Te,chnical Spacifications be changed to read either of the following two ways:
1.
"Confims the accuracy of the. test by ver,1fying that the contaiment leakage rate, L'v, cali:ulated in accordance with ANSI N 45.4 -1982, Appendix C, is within 25 percent of the containment leakage rate, Lv, measured prior to the
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introduction of the superimp~osed leak"; or, 2.
" Confirms the accuracy of the test by verifying that the supplemental test result, Lc, minus the sum of the Type A and the superimposed leak,' Lo, are equal to or less' than O.25 La".
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In addition, it is recommended that Item C.3 of the same surveillance re-
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quirements be changed to read as follows:
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"RequiresVthe & 1 y 4. gas injected inte the contairraent or bled from the containment during the supplemental test
.:* be between 0.75 La and 1.25 La".
The reason for this change' is that App'endix C to ANSI N 4frl(4 - 1972 requires the superimposed leakage rate to be approximately equivalent to La. The new ANSI /ANS 56.8 sets the limits between 0.75 and 1.25 La.
By copy of this memorandum, we recommend that these changes be made a part of the Standard Technical Specifications for both BWR's and PWR's.
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<po My ik Walter R. Butler, Chief W
Containment Systems Branch' J..
Division of Systems Integration cc:
R. Mattson R.- Houston R. Bottimore CS$ Hev.bers C:n ac.t:
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