ML091610066

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Unit 1 - Technical Specification Change 09-10 - Request to Correct Logic Connector Between TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Condition I, Actions 1.2.1 and 1.2.2
ML091610066
Person / Time
Site: Watts Bar Tennessee Valley Authority icon.png
Issue date: 06/05/2009
From: Skaggs M
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
TVA-WBN-TS-09-10
Download: ML091610066 (18)
v • d • e


Text

Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 JUN 0 5 2009 TVA-WBN-TS-09-1 0 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Gentlemen:

In the Matter of the ) Docket No. 50-390 Tennessee Valley Authority )

WATTS BAR NUCLEAR PLANT (WBN) - UNIT 1 - TECHNICAL SPECIFICATION (TS)

CHANGE 09 REQUEST TO CORRECT LOGIC CONNECTOR BETWEEN TS 3.3.2, "ENGINEERED SAFETY FEATURE ACTUATION SYSTEM (ESFAS)

INSTRUMENTATION," CONDITION I, ACTIONS 1.2.1 AND 1.2.2 Pursuant to 10 CFR 50.90, Tennessee Valley Authority (TVA) is submitting a request for TS change (WBN-TS-09-10) to License NPF-90 for WBN Unit 1. The proposed amendment will correct an error by changing a logic connector from "OR" to "AND" between TS 3.3.2, "ESFAS Instrumentation," Condition I, Actions 1.2.1 and 1.2.2. This change will restore consistency with other similar TS actions. This error was apparently introduced during the development of the Unit 1 TSs prior to Unit 1 Licensing but was only recently identified.

The enclosure provides TVA's evaluation of the proposed change. TVA has determined that there are no significant hazards considerations associated with the proposed change and that the TS change qualifies for a categorical exclusion from environmental review pursuant to the provisions of 10 CFR 51.22(c)(9). Additionally, in accordance with 10 CFR 50.91 (b)(1), TVA is sending a copy of this letter and the enclosure to the Tennessee State Department of Public Health.

TVA requests routine processing of this TS change by the NRC and that the implementation of the revised TS be within 30 days of NRC approval.

U.S. Nuclear Regulatory Commission Page 2 June 5, 2009 There are no regulatory commitments associated with this submittal. If you have any questions about this change, please contact Michael Brandon at 423-365-1824.

I declare under penalty of perjury that the foregoing is true and correct. Executed on this 5th day of June, 2009.

Sincerely, Mikeagqg 4 Site Vice Presidednr~-

Watts Bar Nuclear Plant Enclosure cc: See Page 3

Enclosure:

Evaluation of Proposed Change

U.S. Nuclear Regulatory Commission Page 3 June 5, 2009 Enclosure cc (Enclosure):

NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 U.S. Nuclear Regulatory Commission Mr. John G. Lamb, Senior Project Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation MS 0-8 HIA Washington, DC 20555-0001 U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Mr. Lawrence E. Nanny, Director Division of Radiological Health 3 rd Floor L & C Annex 401 Church Street Nashville, Tennessee 37243

ENCLOSURE1 TENNESSEE VALLEY AUTHORITY (TVA)

WATTS BAR NUCLEAR PLANT UNIT 1 WBN-TS-09-10 OPERATING LICENSE NPF-90 EVALUATION OF THE PROPOSED CHANGE

SUBJECT:

TECHNICAL SPECIFICATION 3.3.2, "ENGINEERED SAFETY FEATURE ACTUATION SYSTEM (ESFAS) INSTRUMENTATION" 1.0

SUMMARY

DESCRIPTION This evaluation supports a request to amend Operating License NPF-90 for Watts Bar Nuclear Plant (WBN), Unit 1. The proposed change will correct an error by changing a logic connector from "OR" to "AND" between Required Actions 1.2.1 and 1.2.2 for TS 3.3.2, "ESFAS Instrumentation," Condition I. This change will restore consistency with other similar TS actions.

This error was apparently introduced during the development of the Unit 1 TSs prior to Unit 1 Licensing.

2.0 DETAILED DESCRIPTION This proposed amendment would change the logic connector from "OR" to "AND" between Required Actions 1.2.1 and 1.2.2 of Condition I for TS 3.3.2 as indicated below:

CONDITION REQUIRED ACTION COMPLETION TIME I. One Steam Generator Water 1.1 ----------- NOTE------

Level--High High channel ----

inoperable. One channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing.

Insert "AND" -------------------- 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Delete "OR"

,Place channel in trip.

78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> OR 1.2.1 Be in MODE 3.

84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> OR 1.2.2 Be in MODE 4. to this enclosure provides the markup of the affected TS page. Attachment 2 provides newly-typed version with the above change incorporated. The relevant TS and Bases pages are provided in Attachment 3 as a review aid for this amendment.

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3.0 TECHNICAL EVALUATION

The WBN U1 TSs were developed in the early 1990s. They were based on early versions of the Westinghouse Owners Group (WOG) Standard Technical Specifications (STS)

(NUREG 1431). In preparation for this amendment request, a review of the docketed correspondence was conducted. The following documents were found that documented the evolution of required actions 1.2.1 and 1.2.2 for Condition I:

1) NRC to TVA Letter dated April 2, 1993, requested TVA to review and comment on a "Proof and Review" version of the Unit 1 TSs. In that Proof and Review version, TS 3.3.2, Condition I had only two Required Actions, 1.1, "Place channel in trip." and 1.2, "Be in Mode 3."
2) TVA to NRC Letter dated June 4, 1993 (ML073230460, ML073190382), provided comments on the above "Proof and Review" version. In this submittal, TVA proposed a markup to TS 3.3.2 which broke Required Action 1.2 into two separate Required Actions, 1.2.1, "Be in Mode 3," and 1.2.2, "Be in Mode 4." The logic connector for these actions was proposed to be "AND".
3) NRC to TVA Letter dated October 18, 1995 (ML073200588, ML073460315), transmitted the photo-ready version of the U1 TSs. TS 3.3.2, Condition I in this version contained both Required Actions 1.2.1 and 1.2.2 but with the logic connector "OR".
4) NRC to TVA Letter dated November 9, 1995 (ML020780254), transmitted WBN's low power operating license which contained the issued TSs. TS 3.3.2, Condition I of this version also contained both Required Actions 1.2.1 and 1.2.2 with the logic connector being "OR".

Based on the results of this review, no reason could be found to explain what occurred to cause the incorporation of "OR" rather than "AND" between the proposed markup in Item 2 above and the subsequent revision (Item 3) resulting in the final issue of the Ul TSs (Item 4). However, if compared with other similar actions of TS 3.3.2 (e.g., B.2.1 and B.2.2, C.2.1 and C.2.2, etc.)

and in other TSs, one can see where the actions require the plant to change modes, those actions are connected with an "AND". Further justification for an "AND" connector can be found in the following TS Bases sentence contained in initial November 1995 version which has remained unchanged in the current version of the TS Bases (highlighted version of current Bases page B 3.3-108 is provided in Attachment 3):

"Failure to restore the inoperable channel to OPERABLE status or place it in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> requires the plant to be placed in MODE 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in MODE 4 in the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />." (Emphasis added)

Based on the above, it can be concluded that the appropriate connector should be an "AND" between TS 3.3.2, Condition I, Actions 1.2.1 and 1.2.2.

4.0 REGULATORY EVALUATION

4.1 Applicable Regulatory Requirements/Criteria The regulatory bases and guidance documents associated with the ESFAS functions affected by the proposed change includes: GDC-13 requires that instrumentation shall be provided to El -2

monitor variables and systems over their anticipated ranges for normal operation, for anticipated operational occurrences; and for accident conditions as appropriate to assure adequate safety, including those variables and systems that can affect the fission process, the integrity of the reactor core, the reactor coolant pressure boundary, and the containment and its associated systems.

GDC-20 requires that the protection system shall be designed (1) to initiate automatically the operation of appropriate systems including the reactivity control systems, to assure that specified acceptable fuel design limits are not exceeded as a result of anticipated operational occurrences and (2) to sense accident conditions and to initiate the operation of systems and components important to safety.

GDC-21 requires that the protection system(s) shall be designed for high functional reliability and testability. GDC-22 through GDC-25 and GDC-29 require various design attributes for the protection system, including independence, safe failure modes, separation from control systems, requirements for reactivity control malfunctions, and protection against anticipated operational occurrences.

Implementation of this proposed change will not compromise compliance with the requirements of these documents. Based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

4.2 Precedent WBN TS 3.3.2, Condition I is associated with Function 5.b in Table 3.3.2-1 and is applicable in Modes 1-3 (for reviewer convenience, Page 3 of 7 of WBN Table 3.3.2-1 is provided in ). Function 5.b in WOG STS Table 3.3.2-1, page 6 of 8 (also provided in ) directs one to Condition D (if applicable in Modes 1-3 which would apply to WBN). Upon review of Condition D of the WOG STS, one can find that Condition D would be the same as Condition I upon correction as proposed by this amendment.

In addition, a limited search of the NRC ADAMS Website was conducted but did not reveal any previous precedent involving "OR" and "AND" that would be comparable to this change.

4.3 Significant Hazards Consideration TVA is requesting to amend Operating License NPF-90 for WBN Unit 1. The proposed change will correct an error by changing a logic connector from "OR" to "AND" between Required Actions 1.2.1 and 1.2.2 for TS 3.3.2, Condition I. This change will restore consistency with other similar TS actions. This error was apparently introduced during the development of the Unit 1 TSs prior to Unit 1 Licensing.

TVA has evaluated whether or not a significant hazards consideration is involved with the proposed amendment-by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of Amendment," as discussed below:

1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No.

E1-3

This proposed amendment corrects an identified error by only changing a logic connector between two TS actions. The change only restores the sequential nature of these required actions consistent with other similar TS actions where, if conditions warrant, the movement of the plant to lower modes is required (i.e., to Mode 3, to Mode 4, etc.). In addition, this change does not alter the completion times for these actions. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No.

By correcting the logic connector between these two TS actions, this change only restores consistency with other similar TS actions where movement of the plant to lower modes is required. The change does not alter the expected outcome of the required actions nor does it change the completion times for these actions. Therefore, the possibility of a new or different kind of accident from those previously analyzed has not been created.

3. Does the proposed amendment involve a significant reduction in a margin of safety?

Response: No.

By only correcting the logic connector between the required actions, the proposed change does not alter the expected outcome of the required actions nor does it change the completion times for these actions. Therefore, the proposed change does not involve a significant reduction in a margin of safety.

4.4 Conclusions Based on the above, TVA concludes that the proposed amendment(s) present no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified. In addition, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conduced in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

5.0 ENVIRONMENTAL EVALUATION A review has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed amendment does not involve (i) a significant hazards consideration, (ii)a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.

Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.

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6.0 REFERENCES

a) NRC to TVA Letter dated April 2, 1993 - 'Watts Bar Unit 1 - Proof and Review Version of Technical Specification (TAC M76742)" (A02930408003) b) TVA to NRC Letter dated June 4, 1993 - 'Watts Bar Nuclear Plant (WBN) Unit 1 Technical Specifications - Comments on the Proof and Review" (ML073230460, ML073190382) (T04930604908) c) TVA to NRC Letter dated October 18, 1995 - 'Watts Bar Nuclear Plant (WBN) -

.Photo-Ready Version of the WBN Unit 1 Technical Specifications" (ML073200588, ML073460315) (T04951027241) d) NRC to TVA Letter dated November 9, 1995 - "Issuance of Facility Operating License NPF-20, Watts Bar Nuclear Plant, Unit 1 (TAC M91489)" (ML020780254)

(L44951115002)

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ATTACHMENT 1 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT (WBN)

UNIT I TS-09-10 PROPOSED TS CHANGES (MARKED-UP)

AFFECTED PAGE LIST 3.3-28 MARKED PAGES See aftached.

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

1. One Steam Generator Water 1.1 -- NOTE --------

Level--High High channel One channel may be bypassed inoperable, for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing.

Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR Delete "OR" 1.2.1 Be in MODE 3. 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> 1.2.2 Be in MODE 4. 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> J. One Main Feedwater JA Restore channel to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Pumps trip channel inoperable. OPERABLE status.

Ilnsert "AND", .--

J.2 Be in MODE 3. 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> K. One channel inoperable. K.1 ---------- NOTE --------

One channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing.

Place channel in bypass. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR (continued)

Watts Bar-Unit 1 3.3-28 Amendment 68

ATTACHMENT 2 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT (WBN)

UNIT I TS-09-10 PROPOSED TS CHANGES (RETYPED PAGES)

AFFECTED PAGE LIST 3.3-28 MARKED PAGES See attached.

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

1. One Steam Generator Water 1.1- --------- NOTE --------

Level--High High channel One channel may be bypassed inoperable, for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing.

Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR 1.2.1 Be in MODE 3. 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> AND 1.2.2 Be in MODE 4. 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> J. One Main Feedwater J.1 Restore channel to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Pumps trip channel inoperable. OPERABLE status.

OR J.2 Be in MODE 3. 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> K. One channel inoperable. K.1 ------------ NOTE--------

One channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing.

Place channel in bypass. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR

___________________________(continued)

Wafts Bar-Unit 1 3.3-28 Amendment 68, __

ATTACHMENT 3 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT (WBN)

UNIT 1 TS-09-10 RELEVANT TS AND BASES PAGES (INFORMATION ONLY)

I. AFFECTED PAGE LIST WBN TS Page 3.3-36, Page 3 of 7 WOG STS Page 3.3.2-14, Page 6 of 8 WOG STS Page 3.3.2-2 WOG STS Page 3.3.2-3 WBN TS Bases Page B 3.3-108 II. MARKED PAGES No Change - Relevant areas are highlighted. These pages submitted only as a review aid.

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 3 of 7)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES NOMINAL OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

4. Steam Line Isolation (continued)
c. Containment 1, 2 (c), 3 (c) 4 E SR 3.3.2.1 *2.9 psig 2.8 psig Pressure- SR 3.3.2.4 High High SR 3.3.2.9 SR 3.3.2.10
d. Steam Line Pressure (1) Low 1, 2 (c), 3 (a)(c) 3 per steam D SR 3.3.2.1 > 666.6(b) psig 6 7 5 (b) psig line SR 3.3.2.4 SR 3.3.2.9 SR .3.2.10 (2) Negative 3 (d)(c) 3 per steam D SR 3.3.2.1 _ 108.5 () psi 10 0 c) psi Rate-High line SR 3.3.2.4 SR 3.3.2.9 SR 3.3.2.10
5. Turbine Trip and Feedwater Isolation
a. Automatic 1, 2(M, 3'(f 2 trains H SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Relays
b. SG Water 1, 2(0, 3(f) 3 per SG I SR 3.3.2.1 < 83.1% 82.4%

Level-High SR 3.3.2.4 High(P-14) SR 3.3.2.9 SR 3.3.2. 10

c. Safety Refer to Function I (Safety Injection) for all initiation Injection functions and requirements.

(continued)

(a) Above the P-1 1 (Pressurizer Pressure) interlock.

(b) Time constants used in the lead/lag controller are t, > 50 seconds and t2 - 5 seconds.

(c) Except when all MSIVs are closed and de-activated.

(d) Function automatically blocked above P-1I1 (Pressurizer Interlock) setpoint and is enabled below P-1 I when safety injection on Steam Line Pressure Low is manually blocked.

(e) Time constants utilized in the rate/lag controller are t3 and t4 - 50 seconds.

(f) Except when all MFIVs, MFRVs, and associated bypass valves are closed and de-activated or isolated by a closed manual valve.

(g) MODE 2 if Turbine Driven Main Feed Pumps are operating.

(h) For the time period between February 23, 2000, and prior to turbine restart (following the next time the turbine is removed from service), the response time test requirement of SR 3.3.2.10 is not applicable for 1-FSV 027.

Watts Bar-Unit 1 3.3-36 Amendment 23

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 6 of 8)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER NOMINALO)

SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

4. Steam Line Isolation
h. High High Steam 1,2 (h),3 (h) 2 per D SR 3.3.2.1 5 [130]% of full [ of full steam Flow steam line SR 3.3.2.5 steam flow at full flow at full SR 3.3.2.9 load steam load steam SR 3.3.2.10 pressure pressure Coincident with Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

Safety Injection

5. Turbine Trip and Feedwater Isolation
a. Automatic 1, 2 (i),[3](i) 2 trains H[G] SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.4 and Actuation SR 3.3.2.6 Relays
b. SG Water Level - 1,2 (i),[3 ](1) [3] per SG I[D] SR 3.3.2.1 < (84.2]% [82.4]%

High High (P-14) SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10

c. Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
6. Auxiliary Feedwater
a. Automatic 1,2,3 2 trains G SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.4 and Actuation SR 3.3.2.6 Relays (Solid State Protection System)
b. Automatic 1,2,3 2 trains G SR 3.3.2.3 NA NA Actuation Logic and Actuation Relays (Balance of Plant ESFAS)

(h) Except when all MSIVs are closed and [de-activated].

(i) Except when all MFIVs, MFRVs, [and associated bypass valves] are closed and [de-activated] [or isolated by a closed manual valve].

.-------...........------------------------..... REVIEWER'S NOTE -.-------.......-----------------------------------..

(j) Unit specific implementations may contain only Allowable Value depending on Setpoint Study methodology used by the unit.

WOG STS 3.3.2-14 Rev. 3.0, 03/31/04

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One train inoperable. --------------- NOTE ---------

One train may be bypassed for up to [4] hours for surveillance testing provided the other train is OPERABLE.

C.1 Restore train to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OPERABLE status.

OR C.2.1 Be in MODE 3. 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> AND C.2.2 Be in MODE 5. 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> D. One channel inoperable. [ -- ......-----

The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels.

.----- REVIEWER'S NOTE---------

The below Note should be used for plants with installed bypass test capability:

One channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing.

D.1 Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR WOG STS 3.3.2-2 Rev. 3.0, 03/31/04

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.2.1 Be in MODE 3. 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> AND D.2.2 Be in MODE 4. 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> E. One Containment [ -------- NOTE ---------

Pressure channel One additional channel may be inoperable, bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels.

REVIEWER'S NOTE ----------

The below Note should be used for plants with installed bypass test capability.

One channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing.

E.1 Place channel in bypass. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR E.2.1 Be in MODE 3. 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> AND E.2.2 Be in MODE 4. 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> F. One channel or train F.1 Restore channel or train to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> inoperable. OPERABLE status.

OR F.2.1 Be in MODE 3. 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> AND WOG STS 3.3.2-3 Rev. 3.0, 03/31/04

ESFAS Instrumentation B 3.3.2 BASES ACTIONS H.1, H.2.1 and H.2.2 (continued) assumption that 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is the average time required to perform channel surveillance.

1.1. 1.2.1 and 1.2.2 Condition I applies to SG Water Level-High High (P-14).

If one channel is inoperable, 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> are allowed to restore one channel to OPERABLE status or to place it in the tripped condition. If placed in the tripped condition, the Function is then in a partial trip condition where one-out-of-two logic will result in actuation. The 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> allowed to restore the channel to OPERABLE status or to place it in the tripped condition are justified in Reference

17. Failure to restore the inoperable channel to OPERABLE status or place it in the tripped condition within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> requires the plant to be placed in MODE 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in MODE 4 in the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach MODE 4 from full power conditions in an orderly manner and without challenging plant systems.

In MODE 4, these Functions are no longer required OPERABLE.

The Required Actions have been modified by a Note that allows placing an inoperable channel in bypassed condition for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> while performing routine surveillance testing of other channels. The Note also allows a channel to be placed in bypass for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for testing of the bypassed channel.

However, only one channel may be placed in bypass at any one time. The 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> allowed for testing are justified by Reference 17.

J.1 and J.2 Condition J applies to the AFW pump start on trip of all MFW pumps.

The OPERABILITY of the AFW System must be assured by allowing automatic start of the AFW System pumps. If a channel is inoperable, 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> are allowed to return it to an OPERABLE status. If the function cannot be returned to an (continued)

Watts Bar-Unit 1 B 3.3-108 Revision 90 Amendment 68

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